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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 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges: | | {{#Wiki_filter:}} |
| Alex S. Karlin, Chairman Dr. Richard E. Wardwell Dr. William H. Reed In the Matter of )
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| )
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| ENTERGY NUCLEAR VERMONT YANKEE, LLC ) Docket No. 50-271-LR and ENTERGY NUCLEAR OPERATIONS, INC. ) ASLBP No. 06-849-03-LR (vermont Yankee Nuclear Power Station) ))
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| NEW ENGLAND COALITION, INC.
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| CONTENTIONS 2A and 2B PREFILED EXHIBITS NEC-JH 03- NEC-JH 24 April 28, 2008 Volume 1
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| NEC-JH_03
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| 'V Review of Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. ("Entergy") 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
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| TABLE OF CONTENTS I. B A CK G R O UN D ................................................................................ 1 A . B asic T echnical Principles ............................................................ 1 B. Regulatory Requirements ........................................................... 2 II. ENTERGY'S CUFen ANALYSES ......................................................... 4 A . B rief History ................................................................. ......... 4 III. ASSESSMENT OF ENTERGY'S CUFen REANALYSES ........................ 8 A . Incom plete Inform ation ............................................................ 8 B . E ntergy's A ssumptions ............................................................... 9 C. Assessment of Assumptions ........................................................ 10
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| : 1. Environmental Correction Factor, Fen ................................... 10
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| : 2. H eat Transfer .............................................................. 12
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| : 3. B ase M etal C racks ......................................................... 15
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| : 4. N um ber of Transients ...................................................... 16
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| : 5. O xygen ................................................................... 16
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| : 6. Green's F unction ........................................................... 17 D . Lack of Error A nalysis .............................................................. 18 E. "Confirmatory" Analysis of Feedwater Nozzle .................................. 18 IV. HOPENFELD CUFen RECALCULATION ............................................ 19 V . SU M MA RY .................................................................................... 20 V I. R E F E R EN C E S............................................................................. 21 VII. GLOSSARY OF TERMS ................................................................. 22
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| 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.
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| During each loading cycle, some fraction of the component's fatigue life is exhausted, its size depending on the magnitude of the applied stress.
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| 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.
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| 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.
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| 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)
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| Fen is derived from laboratory data on the effect of strain on fatigue life, i.e.
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| the number of cycles to failure. NUREG/CR-6909 describes such laboratory tests in detail.
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| 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.
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| 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
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| ("TLAA") for components covered by the license renewal regulations.1 If TLAAs are defined as:
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| Those licensee calculations and analyses that:
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| (1) Involve systems, structures, and components within the scope of license renewal, as delineated in § 54.4(a);
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| (2) Consider the effects of aging; (3) Involve time-limited assumptions defined by the current operating term, for example, 40 years; (4) Were determined to be relevant by the licensee in making a safety i
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| 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
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| 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).
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| NUREG- 1801, Rev. 1, Generic Aging Lessons Learned (GALL)
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| 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-
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| : 2. As explained further in industry guidance document MRP-47:
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| 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.
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| 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].
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| 2 NUREG- 1801 is referenced with approval in Regulatory Guide 1.188, Rev. 1, StandardFormatand Contentfor Applications to Renew Nuclear Power Plant Operating Licenses (2005) ("Reg. Guide 1.188").
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| 3
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| 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.
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| 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.
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| 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.
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| The five elements of Entergy's initial reanalysis included:
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| I 3 MRP-47, Revision 1, Electric Power Research Institute, MaterialsReliability Program:
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| Guidelinesfor Addressing FatigueEnvironmental Effects in a License Renewal Application at 3-4 (2005).
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| 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.
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| 5 LRA at 4.3-7.
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| 6 These reports are submitted in this proceeding as Exhibits NEC-JH_04 - NEC-JH_21.
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| I 4 1
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| : 1. Development of a finite element model
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| : 2. Development of heat transfer coefficients
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| : 3. Development of Green Functions
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| : 4. Development of thermal transient definitions
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| : 5. Performance of Stress and Fatigue Analysis.
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| Entergy reported the results of its initial reanalysis in the Table 1, reproduced below:
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| TABLE 1 VYNPS Cumulative Usage Factors for NUREG/CR-6260 Limiting Locations 7 Material Overall*
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| 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.
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| 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 9
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| referencing Green's function."
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| ' Exhibit NEC-JH_35 at Attachment 2.
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| 8 FSER, NRC Staff Exhibit 01 at 4-40.
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| 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).
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| 5
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| I At the February 7, 2008 meeting of the ACRS, which I attended, the I
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| NRC Staff informed the ACRS that it was satisfied with the CUFen calculations based on Entergy's then-reported "confirmatory" results for the I 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, I
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| substituting a different Fen value. Specifically, NRC Staff requested use of "the maximum Fen value used in [Entergy' s] previous analyses," rather than I "different, but appropriate" Fen values Entergy had used in its "confirmatory" analysis.'0 I
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| The following Table 2 summarizes how Entergy's reported CUFen values for the feedwater nozzle have changed with each iteration of its I analysis.
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| Table 2- CUFen Calculations For the Feedwater Nozzle REFERENCE CUF Fen CUFen I
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| License Renewal Application Table 4.3-3 0.750 3.81 2.86 I
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| Entergy Initial CUFen Reanalysis Using Simplified Green's Function.
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| NEC Exhibit JH_18 at 3-18, Table 3-0.0636 10.05 0.6392 I
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| 10.
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| Entergy "Confirmatory" CUFen 0.0889 3.97 0.3531 I Reanalysis.
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| NEC Exhibit JH 21 at 7, Table 1.
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| Adjusted "Confirmatory" Reanalysis 0.8930 I result verbally provided during February 14, 2008 NRC Staff audit of Entergy's "Confirmatory" Reanalysis. I FSER, NRC Staff Exhibit 1 at 4-42.
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| I A comparison of Entergy's result using the simplified Green's function method, 0.639, with its "confirmatory" result, ultimately 0.8930 as I recalculated February 14, 2008, demonstrates that the simplified Green's I
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| "OFSER, NRC Staff Exhibit 01 at 4-42.
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| I 6 I
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| 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."'14 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."'15 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.
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| I1d. at 4-43.
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| 13 Id.
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| 14 Exhibit NEC-JH-23 at 2.
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| 15 Id.
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| 16 Exhibit NEC-JH_24.
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| 7
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| 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.
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| 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:
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| : 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. 17 This information is necessary to validate I the assumption of uniform heat transfer distribution.
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| : 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.
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| ("SIA") report of Entergy's initial CUFen reanalysis, VY-16Q-307:
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| 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:
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| l7 Exhibit NEC-JH_25 is illustrative of the layout drawings Entergy produced to NEC.
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| I I
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| 8!
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| 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:
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| 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.
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| B. Entergy's Assumptions Both Entergy's Initial and "Confirmatory" CUFen Reanalyses incorporated the following assumptions:
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| : 1. The environmental correction factor, Fen, depends only on the temperature, the dissolved oxygen, the sulphur content and the strain rate.
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| 18 Exhibit NEC-JH_10 at 12-13 (emphasis added).
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| 9
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| : 2. With respect to determination of the heat transfer coefficients in all I three nozzles:
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| I
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| : a. Nozzle entrance and exit effects can be neglected
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| : b. Water properties do not change with temperature
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| : c. Uniform circumferentially.
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| : 3. The base metal under the cladding at the feedwater blend radius has no cracks.
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| : 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.
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| : 5. The oxygen at the surface of any component can be evaluated based I on plant records, using the EPRI -BWRVIA computer code.
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| Entergy's Initial CUFen Reanalysis also included the following additional assumption:
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| : 6. Green's functions can be used as a substitute for the ASME Code Section III, Subsection NB-3200 method.
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| 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.
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| : 1. Environmental Correction Factor, Fen i Entergy calculated the Fen parameters based on outdated Argonne National Laboratory (ANL) statistical equations stated in N-UREG/CR 6583 3
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| and NUREG/CR 5704 ("the NUREG equations"), which were derived more
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| '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.").
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| I 10
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| 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.
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| The developer of the revised ANL equations, 0. Chopra, stated to the ACRS:
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| 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 22 mean stress, surface finish, size, and loading history.
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| This same caveat is repeated in NUREG/CR-6909. To account for uncertainties, the NUREG report states:
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| "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."
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| 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.
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| 21 Exhibit NEC-JH_26.
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| 22 Exhibit NEC-JH_27 at 22.
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| 23 Exhibit NEC-JH_26 at 62.
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| 24 Exhibit NEC-JH_26 at 14.
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| 11
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| 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).
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| 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.
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| 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. 25 The Staff stated that the new data will apply to new reactor applications.26 It would appear that it would be equally important, if not more important, to apply the new data to a 40 year reactor.
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| : 2. Heat Transfer Entergy used the following heat transfer equations to calculate the thermal stress for each transient:
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| : 1. h 0.023 (Re )-8 (Pr).4 k/D 27
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| : 2. h 0.55 (GrPr) 25 k/L 28 U
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| : 3. h= 0.555 ( R ( R-Rs)gk 3 hfg/ ( ud del T ) ).25 (R=-rho, u =mu) 29 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.
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| 26 Id.
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| 27 Exhibit NEC-JH_04 at 11, Table 4. 1 28 Exhibit NEC-JH_14 at 14.
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| 29 Exhibit NEC-JH_19 at 7.
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| 12 I[
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| 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 32 each transient.
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| Page 212 of Reference 2 also provides such a correction.
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| 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
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| .. .. ....
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| the nozzle. As shown in Reference 3 and the above sketch, the velocity distribution in the nozzle will vary circumferentially. 33 Such flow distribution would lead to circumferentially varying wall temperature and different stress distribution than would be predicted by an axixsymetrical model.
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| 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.
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| 31 Exhibit NEC-JH_29.
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| 32 Id.
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| " Exhibit NEC-JH_30.
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| 13
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| 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.
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| 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.
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| 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. 34 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.
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| 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.
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| The following statement quoted from one report of Entergy's initial CUFen reanalysis demonstrates that Entergy ignored the inherently local feature of natural convection:
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| 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 35 as the free convection heat transfer coefficient.
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| Such a procedure is appropriate for the determination of overall heat balances but not for the determination of stress distributions.,
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| 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.
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| 14 Exhibit NEC-JH_14 at 14.
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| 35 Id.
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| 14
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| 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.
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| 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. 36 Throughout its analyses, Entergy used location-independent heat transfer coefficients, which is inappropriate, as I have explained in the above discussion.
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| : 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.
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| In RAI 4.3-H-02, VY admitted that the cladding may contain cracks, 37 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". 38 Since Ultrasonic Inspection, UT, measures only the total length of a crack and, based on the VY drawings 39 Entergy has produced, the exact thickness of the clad is not known, 36 Exhibit NEC-JH_13 at 26.
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| 37 Exhibit NEC-JH_32.
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| 38 Exhibit NEC-JH_33 at 4.
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| 39 Exhibit NEC-JH_25.
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| 15
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| 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.
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| : 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.
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| 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
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| : 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
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| 16 i
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| electrochemical potential measurements relate to the oxygen concentration at the component surface during transients.
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| 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 40 surface of a given component.
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| 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.42 Entergy did not describe how the BWRVIA code was benchmarked.
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| 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.
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| : 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. 43 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.
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| 41 Exhibit NEC-JH_ 35.
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| 42 Id.
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| 43 See, e.g., Exhibit NEC-JH_04.
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| 17
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| 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.
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| 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, 44 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.
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| 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.45 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.
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| 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.
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| 5 Exhibits NEC-JH 19 - NEC-JH 21.
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| I 18i
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| the CUFs. Entergy did not discuss these differences; instead it only provided the following vague and unscientific statement:
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| 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.
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| 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.
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| 46 Exhibit NEC-JH 35 at Attachment 1.
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| 19
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| I I
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| TABLE 3 - Recalculated Cumulative Usage Factors for Sample Locations at VYNPS I
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| No. NUREG/CR-6260 Sample CUF (VYNPS Lice:nse Fen Recalculated CUFen U.
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| Location (License Renewal Renewal Applicati( )n, (Ref. 1)
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| Application, Table 4.3-3) Table 4.3-3) 1 Vessel shell & bottom head 0.400 17 6.80 -
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| i U 2 Core spray safe end 0.182 12 2.18 is
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| '3 Feed water nozzle 0.750 17 12.75 i - M 4 RHR return Piping r- - - ---- - - -
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| 0.032 12 0.38 I 65 i RR inlet nozzle 0.610 17 10.37 16 : RR piping tee F ]
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| 0.397 12 4.76 I
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| 17 1RR outlet nozzle 0.810 17 13.77 8Core spray nozzle 0.625 17 10.62 I
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| *9 iFeed water piping 0.427 17 7.26 U
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| V.
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| ==SUMMARY==
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| By introducing five key assumptions, excluding those connected with I
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| 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 I 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 I
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| components exceeds unity.
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| I 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 I
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| its "confirmatory" analysis demonstrate that CUFens for the components listed in License Renewal Application 4.3-3 or NUREG/CR-6260 limiting I 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.
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| I I
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| 20 I
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| 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.
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| VI. REFERENCES
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| : 1. J. P. Holman, Heat Transfer, 1981 Ed.
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| : 2. E. R. G. Eckert and R. Drake, Heat and Mass Transfer 2' nd, Ed 1959.
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| : 3. H. Schlichting, Boundary Layer Theory, 4th Ed. 1960.
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| : 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.
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| : 5. NUREG/CR-6583, "Effect of LWR Coolant Environment on Fatigue-Design Curves of Carbon and Low Alloy Steels," March 1998.
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| : 6. NUREG/CR 5704, "Effect of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steel," April 1999.
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| : 7. NUREG/CR-6936, "Probability of Failure and Uncertainty Estimate for Passive Components - A Literature Survey," May 2007.
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| 21
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| VII. GLOSSARY OF TERMS Cumulative Usage Factor (CUF) - A summation of usage fatigue factors.
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| 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.
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| 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.
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| Recirculation Nozzle - A short pipe welded to the reactor vessel through n which water flow either in or out of the jet pump.
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| Spray Nozzle - A nozzle on top of the vessel used to cool the core in case of I an accident.
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| Transient - Plant response to a change in power level.
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| 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.
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| 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.
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| 2 22
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| StructuralIntegrityAssociates, Inc. File No.: VY-16Q-301 NEC-JH_04 CALCULATION PACKAGE 'Project No.: VY-i6Q PROJECT NAME:
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| Environmental Fatigue Analysis of VYNPS CONTRACT NO.:
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| 10150394 CLIENT: PLANT:
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| Entergy Nuclear Operations, Inc Vermont Yankee Nuclear Power Station CALCULATION TITLE:
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| Feedwater Nozzle Stress History Development for Green Functions Document Affected Project Manager Preparer(s) &
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| Revision Pages Revision Description . Approval. Checker(s)
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| Signature & Date Signatures& Date 0 1-27, Initial Issue Terry J. Herrmann Appendix: 07/12/2007 -,
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| Al-A2 Minghao Qin 07/11/07 John F. Staples 07/11/07 Page 1 of 27 F0306-O I RO
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| StructuralIntegrityAssociates, Inc. I I
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| Table of Contents I
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| 1.0 O BJECTIV E ........................ . .............................................
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| 2.0 FEEDWATER NOZZLE MODEL ......................................................................................
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| 4 4
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| I 3.0 A PPL IED L OA D S....................................................................... .............................................. 4 4.0 THERMAL AND PRESSURE LOAD RESULTS ............................... 7 I 5.0 REFE RE N C E S ........................................................................... ............................................... 9 APPENDIX A FINITE ELEMENT ANALYSIS FILES ............................. Al I I
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| I List of Tables I
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| Table 1: M aterial Properties @ 300'F .......................................................................................... 10 Table 2:
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| Table 3:
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| Nodal Force Calculation for End Cap Load ................
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| Pressure R esults ....................................................................................................................
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| 10 11 I
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| 0.................
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| Table 4: Heat Transfer Coefficients for Region 1 (40% Flow) ................................... ....................... 11 I
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| I I
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| I I
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| I I
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| File No.: VY-16Q-301 Page 2 of 27 I
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| Revision: 0 F0306-01 RO I
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| Structural IntegrityAssociates, Inc.
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| I
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| ! iAist of Figures Figure 1: ANSYS Finite Element Model ......................... ............ ......................................... 12 Figure 2: Feedwater Nozzle Internal Pressure Distribution ........................................................ 13 Figure 3: Feedwater Nozzle Pressure Cap Load.......................................................................... 14 Figure 4: Feedwater Nozzle Vessel Boundary Conditions ........................................................... 15 Figure 5: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries [1] ......... ......... 16 Figure 6: Safe End Critical Thermal Stress Location ........... ................................... 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 .......... ................................. 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.
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| 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 Page 3 of 27 Revision: 0 F0306-01 RO
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| StructuralIntegrityAssociates, Inc..
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| 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.
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| 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.
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| 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:
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| Feimenien = r(IR)2 P - )
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| where:
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| 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 R0 = Outside Radius of element that node is attached to Fnode = The average of the element forces on either side of the node..
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| Note.: The force on the innermost and outermost nodes is calculatedas one halfof the force on the element that they are attachedto. 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 Revision: 0 Page 4 of 27 I F0306-OIRO m
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| I V StructuralIntegrityAssociates, Inc.
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| nozzle geometry as well as the pressure Ic)ading. Figures 2, 3, and 4 show the internal pressure distribution, cap load, and symmetry conclition applied to the vessel end of the model, respectively.
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| 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.
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| 3.2.1 Heat Transfer Coefficients Referring to Figure 5, heat transfer coefficients were applied as following:
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| Region 1 The heat transfer coefficient, h. for 100% flow is 3705 BTU/hr-ft2 -OF at 3000 F. [1, Table 5]
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| The heat transfer coefficient, h, for 40% flow is 1780 BTU/hr-ft2 -OF at 300TF. [Table 4]
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| The heat transfer coefficient, h, for 25% flow is 1222.2 BTU/hr-ft2 -OF at 300 0 F. [1, Table 4]
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| 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.
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| Region 3 The heat transfer coefficient, h, for 100% flow is 1489 BTU/hr-ftZ-°F at 3000 F. [1, Table 9]
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| The heat transfer coefficient, h, for 40% flow is 743 BTU/hr-ft 2-F at 300TF. [1, Table 9]
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| The heat transfer coefficient, h, for 25% flow is 504 BTU/hr-fi2-F at 300 0 F. [1, Table 9]
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| Region 4 File No.: VY-16Q-301 Page 5 of 27 Revision: 0 F0306-01 RO
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| StructuralIntegrity 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.
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| Region 5 The heat transfer coefficient, h, for 100% flow is 177.4 BTU/hr-ft2 -F at 300 0 17. [1, Table 16]
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| The heat transfer coefficient, h, for 40% flow is 88.5 BTU/hr-ft 2 -°Fat 300 0 F. [1, Table 16]
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| The heat transfer coefficient, h, for 25% flow is 60 BTU/hr-ft2 _-F at 300TF.[1, Table 16]
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| 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.
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| Region 7 Per Reference [1], the heat transfer coefficient for Region 7 (reactor vessel inside wall) is a .
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| constant of 864 BTU/hr-ft2 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-ft2 -OF [1].
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| 3.2.2 Boundary Fluid Temperatures For the Green's Functions, a 500°F - 100IF 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:
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| Regions I to55 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
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| UStructural IntegrityAssociates, Inc.
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| I I 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 FWT-VY_100.INP, FWTVY_40.INP, and FWTVY_25.INP for 100%, 40%, and 25% full flow rate, respectively.
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| 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.
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| * The critical safe end location was chosen as node 192, which has the highest stress intensity due to
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| * 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.
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| The critical blend radius location was chosen, based upon the highest pressure stress.
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| 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.
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| 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
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| * 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.
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| The stress time history for the critical paths was extracted during the stress run for 100% flow rate.
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| * This produced two files, HFSE.OUT and HFBLEND.OUT, which contain the thermalstress history.
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| The membrane plus bending stresses and total stresses for the Green's Functions were extracted.
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| from these files to produce the files HFSEInside.RED and HFBLENDInside.RED, where SE and.
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| BLEND corresponded to the safe end and blend radius locations, respectively.
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| The stress time history for the critical paths was extracted during, the stress run for 40% flow rate.
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| 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.
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| I The stress time history for the critical paths was extracted during the stress run for 25% flow rate.
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| This produced two files, LFSE.OUT and LFBLEND.OUT, which contain the thermal stress history.
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| 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.
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| I File No.: VY-16Q-301 Page 7 of 27 Revision: 0 F0306-OIRO
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| StructuralIntegrity 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. .
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| 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.
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| 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.
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| intensity at Node 192 and Node 657 were determined to be 8,693 and 27,490 psi, respectively.
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| 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 multiplier on the vessel radius. These results are contained in the file, PVESS.OUT. Based on I
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| 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.
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| The equation for the membrane hoop stress for a sphere is:
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| (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.
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| The equation for the membrane hoop stress in a cylinder is:
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| (pressure) x (radius) thickness i File No.: VY-16Q-301 Page 8 of 27 Revision: 0 F0306- OIRO
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| I StructuralIntegrityAssociates, Inc.
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| 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.
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| 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.
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| ==5.0 REFERENCES==
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| : 1. SI Calculation No. VY- IOQ-301, Revision 0, "Feedwater Nozzle Finite Element Model and Heat Transfer Coefficients."
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| : 2. ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004.
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| : 3. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition, 2000 Addenda.
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| : 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.
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| : 5. J. P. Holman, "Heat Transfer," 4th Edition, McGraw-Hill, 1976.
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| : 6. J. P. Holman, "Heat Transfer," 5th Edition, 1981.
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| : 7. GE Nuclear Energy Certified Design Specification, "Reactor Vessel - Extended Power Uprate,"
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| Revision 1, SI File No. VY-05Q-236.
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| : 8. N. P. Cheremisinoff, "Heat Transfer Pocket Handbook," Gulf Publishing Co, 1984.
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| File No.: VY-16Q-301 Page 9 of 27 Revision: 0 F0306-OI RO
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| I Table 1: Material Properties @ 300'F (1) I Instantaneous Young's Coefficient of Density, Conductivity, Diff-usivity, Specific Heat, Poisson's Material Modulus, Thermal P (lb/in 3 )
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| *k d j C Ratio I
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| Ident. E x 106 (psi)
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| _________________________
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| Expansion, a x 10-6 0
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| (in/in- F)
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| (assumed)
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| (BTU/hrft.F)
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| ('
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| (f,'hr)
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| I_______
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| (BTU/Ibm-°F)
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| (see Note 5) (assumed)
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| I SA533 Grade B, A508 Class 11 26.7 7.3 0.283 23.4 0.401 0.119 0.3 (see Note 2)
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| SS Clad (see Note 3) 27.0 9.8 0.283 9.8 0.160 0.125 0.3 H
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| A508 Class I (see Note 4)
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| AI06 Grade B" 28.1 28.3 7.3 7.3 0.283 0.283 32.3 32.3 0.561 0.561 0.118 0.118 0.3 0.3 I
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| (see Note 4)
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| Notes I
| |
| : 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 I code is acceptable since later editions typically reflect more accurate material properties than was published 2.
| |
| 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].
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| Properties of A508 Class II are used (3/4Ni-I/2Mo-lI/3Cr-V).
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| I
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| : 3. Properties of 18Cr- 8Ni austenitic stainless steel are used.
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| 4.
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| 5.
| |
| Composition = C-Si.
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| Calculated as [k/(pd)]/12 3 . I Table 2: Nodal Force Calculation for End'Cap Load I Node Number Element Number Radius (in)
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| A Radius (in)
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| R o2-Ri 2 (in2 Felement (lIb)
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| Fnode (Ilb)
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| I 1 5.42 : 7678.0 2
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| 1022 5.3029 0.1171 1.25565 15356.1 15188.4 I
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| 1021 0.1171 1.22823 15020.7 3
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| 1020 5.1858 _
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| 0.1171 1.20080 14685.3 14853.0 I 4 5.0687 14517.6 5
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| 1019 4.9516 0.1171 1.17338 14349.9 14182.2 I
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| 1018 0.1171 1.14595 14014.5 6 4.8345 1 1 1 7007.3 I
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| File No.: VY-16Q-301 Page 10 of 27 I
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| Revision: 0 F0306-01 RO I
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| I Table 3: Pressure Results Membrane Plus Total Stress Location Bending Stress Intensity (psi)
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| Intensity (psi)
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| 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.
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| Table 4: Heat Transfer Coefficients for Region 1 (40% Flow)
| |
| Calculation of Heat Transfer Coefficients for FeedwaterNozzle Flow Path Pipe Inside Diameter, D inches 0.806 ft 100% rated flow = 4,5110 gpm 0.246 m @T 311,91 "F Flow, % of rated = -li Density. a = *.53.8897j_, 1lbm,3 Fluid Velocity, V = 8.022 flsec = 1,826.0 gpm= 0.793742524 MIb/hr Characteristic Length, L = D 0.806 ft= 0 246 m T - T., AT = assumed to be 12% of fluid temperature = 8.40 12.00 24.00 .36.00 48.00 60.00 72.00 " F
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| _,_____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
| |
| ....The..... _a
| |
| ......C * . .*.............. ....... .......................
| |
| . . . 0,* . ...........
| |
| .:._* _0.90
| |
| ;920 q ...
| |
| -q................
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| *.3q,* .... .. . 03239 0. . . ... :* . . . .. 0:.3 _ _...
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| _-_ .- _-_
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| .(I..C ýytyý -. 3L46 0.60 . 35 03 0.2930 Btu.1,r-ft-TF 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' 5
| |
| (Density) 62.3 62.1 60.1 57.3 53.6 49.0 42.4 Ibm/ft 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
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| ------- )..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 -
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| (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 -
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| Grashof Number, Gr g*tnTL3/(pWp), 1.2852E+08 6.6834E+08 1.2721E+10 6.5918E+10 2.0931E+11 5.4429E+11 1.1372E+12 -
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| Raleigh Number Ra GrPr 8.9710E+08 3.0142E+09 2.4297E+10 8.0420E+10 1.9885Et11 4.6755E+11 1.2166E+12 -
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| trom [5]:.
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| Inside Surface Forced Convection Heat Transfer Coefficient:
| |
| 58 Hy,. = 0.023Re Pr°-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 From [51."
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| 1.4EO _-ý4- 91EA ~3 434E-03~< 3.724E-03., 3.1E0 3 SE0 tu/sec-in'-*F Inside Surface Natural Convection Heat Transfer Coefficient:
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| Case: Enclosed cylinder C= r, .* n: eMo 16))
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| H- C(GrPr)nk.L 232.43 330.57 599.85. 15.28 988.69 1,118.84 1,192.73
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| '40.3 2 10864>*÷ 143.58 174.12 K'1968994,:,:1 210.06/ Gtu/ýr-ft'.F 7ý836E8(85 I3ý.L -O4.'>.2,0136E-04 2.7,NE-4.7 3.355JE04AK :3,800E, 01 ~4062E.104' 4 use-n File No.: VY-16Q-301 Page I I of 27 Revision: 0 F0306-0 1RO
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| StructuralIntegrityAssociates, Inc.
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| ELEMENTS AU.*,S I*i SEP 6 2002 16:23:51 Y
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| Feedwater Nozz1e'FT-ite Element Model Figure 1: ANSYS Finite Element Model File No.: VY-16Q-301 Page 12 of 27 Revision: 0 F0306-01 RO
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| i ELEMENTS AUN SEP 13 2002 PRES-NORM 12:16:11 1000
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| /
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| '1 I
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| Feedwater Nozzle Finite Element Model I Figure 2: Feedwater Nozzle Internal Pressure Distribution File No.: VY-16Q-301 Page 13 of 27 Revision: 0 F0306-O1RO
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| StructuralIntegrity Associates, Inc.
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| Figure 3: Feedwater Nozzle Pressure Cap Load File No.: VY-16Q-301 Page 14 of 27 Revision: 0 F0306-O1RO
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| *Structural IntegrityAssociates, Inc.
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| V ELEMENTS 7AN\Y SEP 13 2002 p 12:20:02 Feedwater Nozzle Finite Element Model Figure 4: Feedwater Nozzle Vessel Boundary Conditions File No.: VY-16Q-301 Page 15 of 27 Revision: 0 F0306-O1RO
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| StructuralIntegrity Associates, Inc.
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| I RegIan 7 I
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| Region 8 I
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| -F I I
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| Region 6 Region I ~ ' Region 4 Region 5 I Ail eke Notes: Point A: End of thermal sleeve = Node 204 = 0.25" from feedwater inlet side of thermal sleeve flat.
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| I Point B: Beginning of annulus = Node 252.
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| Point C: Beginning of thermal sleeve transition = approximately 4.0" from Point A = Node 294.
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| Point D: End of thermal sleeve transition = approximately 9.5." from Point A = Node 387.
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| Point E: End of inner blend radius (nozzle side) = Node 553.
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| I Point F: End of inner blend radius (vessel wall side) = Node 779.
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| Figure 5: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries [11 U I
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| I I
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| File No.: VY-16Q-301 Revision: 0 Page 16 of 27 I F0306-OIRO I
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| I 1VS~V~. ]A206 7.~.. 28~JO?
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| 71'57 21254 -535:1 *'A9 A7 G3,5
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| .4*
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| F6dwateir>NozzIe .Finite E'lenierit Mo.
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| del, Figure 6: Safe End Critical Thermal Stress Location File No.: VY-16Q-301 Page 17 of 27 Revision: 0 F0306-01 RO
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| StructuralIntegrityAssociates, Inc. I l
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| *ANSYSý ý1AL MAR9 2o007,:
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| MAT, -NUM 13:,25: 09 Figure 7: Safe End Limiting Linearized Stress Paths File No.: VY-16Q-301 Page 18 of 27 Revision: 0 F0306-01 RO
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| Figure 8: Blend Radius Limiting Pressure Stress Location File No.: VY-16Q-301 Page 19 of 27 Revision: 0 F0306-0 1RO
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| 19 200O7 1D:36: 47.
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| Feedwater, Nozzle -Jnite Eement Model Figure 9: Blend Radius Linearized Stress Path File No.: VY-16Q-301 Page 20 of 27 Revision: 0 F0306-01 RO
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| Total Stress Intensity 70000 a-0 100 200 300 400 500 Time (sec)
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| Figure 10: Safe End 100% Flow Total Stress Intensity Total Stress Intensity a-U, 0 100 200 300 400 500 Time (sec)
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| Figure 11: Blend Radius 100% Flow Total Stress Intensity File No.: VY-16Q-301 Page 21 of 27 Revision: 0 F0306-O1RO
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| Structural integrity Associates, Inc.
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| Total Stress Intensity a.
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| cn 0 100 200 300 400 500 Time (sec)
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| Figure 12: Safe End Total Stress History for 100% Flow Total Stress Intensity I
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| I I
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| a.
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| I I
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| I 0 100 200 300 400 500 Time (see)
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| Figure 13: Safe End Membrane Plus Bending Stress History for 100% Flomge 22 of 27 I File No.: VY-16Q-301 Pa*
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| Revision: 0 F0306-O1RO
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| Total Stress Intensity 500G0 20000 0 100 200 300 400 500 Time (sec)
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| Figure 14: Safe End Total Stress History for 40% Flow Total Stress Intensity 40000 0~
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| (6 0 100 200 . 300 400 500 Time (sec)
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| Figure 15: Safe End Membrane Plus Bending Stress History for 40% Flow File No.: VY-16Q-301 Page 23 of 27 Revision: 0 F0306-OI RO
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| I I
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| Total Stress Intensity I
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| 400
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| -sz-sx I
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| 300(
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| K)O I
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| 20 I
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| 1000O0 I
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| 0 ....
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| ,-10300 I
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| 0V 0 100 200 300 400 50O0I Time (sec)
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| Figure 16: Safe End Total Stress History for 25% Flow I Total Stress Intensity I I
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| I C- I I
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| I 100 200 Time (sec) 300 400 500 I Figure 17: Safe End Membrane Plus Bending Stress History for 25% Flow File No.: VY-16Q-301 Pai ge 24 of2 I Revision: 0 F0306-O1R0RO
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| StructuralIntegrityAssociates, Inc.
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| I Total Stress Intensity 30000 25000 20000 15000 10000 5000-1000 2000 3000 4000 5000 Time (sec)
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| Figure 18: Blend Radius Total Stress History for 100% Flow Total Stress Intensity 15000 0) 0 1000 2000 3000 4000 5000 Time (sec)
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| Figure 19: Blend Radius Membrane Plus Bending Stress History for 100% Flow File No.: VY-16Q-301 Page 25 of 27 Revision: 0 F0306-OI RO
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| I Total Stress Intensity 30000 I 25000- I
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| / szs 20000 I
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| 15000 I
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| 10000 I
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| .0 I
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| 0 1000 2000 3000 4000 5000O Time (sec)
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| I Figure 20: Blend Radius Total Stress History for 40% Flow Total Stress Intensity I
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| I I
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| 15000 I
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| I I
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| 0 1000 2000 3000 4000 5000 o I Time (sec)
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| Figure 21: Blend Radius Membrane Plus Bending Stress History for 40% Fi ge 26of 27 I File No.: VY-16Q-301 Pa*
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| Revision: 0 F03 06-01] RO
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| StructuralIntegrityAssociates, Inc.
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| Total Stress Intensity 30000 25000 20000 ( -4 1______________ ______________ -sz.sx 15000 Un 10000 5000 0 1000 2000 3000 4000 5000 Time (sec)
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| Figure 22: Blend Radius Total Stress History for 25% Flow Total Stress Intensity 30000 25000 200 00 ___
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| a I 150 00 __________
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| U) 100(
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| 50(
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| 0 1000 2000 3000 4000 5000 Time (sec)
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| Figure 23: Blend Radius Membrane Plus Bending Stress History for 25% Flow File No.: VY-16Q-301 Page 27 of 27 Revision: 0 F0306-01 RO
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| I I
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| APPENDIX A FINITE ELEMENT ANALYSIS FILES File No.: VY-16Q-301 Page Al of A2 Revision: 0 F0306-OI RO
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| . ' Structural Integrity Associates, Inc.
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| 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
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| #FBLEND.OUT Stress Output at Blend Radius In Computer files
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| #FSE INSIDE.RED Stress Extracted at Safe End In Computer files
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| #FBLEND INSIDE.RED Stress Extracted at Blend Radius In Computer files
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| #FSE T-Green.XLS Green Function with Total Stress at Safe End In Computer files
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| #FSE_M+B-Green.XLS Green Function with Membrane plus Bending Stress In Computer files at Safe End
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| #FBR T-Green.XLS Green Function with Total Stress at Blend Radius In Computer files
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| #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 Page A2 of A2 Revision: 0 F0306-O I RO
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| | |
| [ StructuralIntegrityAssociates, Inc.
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| CALCULATION PACKAGE File No.: VY-16Q-302 Project No.: VY-16Q NEC-JH 05 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
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| StructuralIntegrityAssociates, Inc.
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| I I
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| Table of Contents I
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| 1.0 OBJECTIVE ..................... I..........................................................................................................
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| 2.0 M ETHODOLOGY ....................................... .. .... . ......................
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| . ........................................... 4 44 I
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| 7 3.0 4.0 ANALYSIS ....................................................................... .....................................................
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| FATIGUE USAGE RESULTS................................................................................................ 11 I 5.0 ENV IRONM ENTAL FATIGUE ANALYSIS ........................................................................... I1
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| | |
| ==6.0 REFERENCES==
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| .................................................................. ..........................................................
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| APPENDIX A SUM MARY OF OUTPUT FILES ....................................................................
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| 12 Al I
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| I I
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| List of Tables I
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| Table 1: B lend Radius Transients ..................................................................................................
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| Table 2: Safe End Transient ..........................................................................
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| 14
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| ........ ....... ........... 14
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| ,I Table 3: Maximum Piping Stress Intensity Calculations ............................................................
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| Table 4: Blend Radius Stress Summary ..........................................
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| 15 16 U
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| Table 5: Safe End Stress Summary .................... I ......................... o..18 Table 6: Fatigue Results for Blend Radius (60 Years) ....................... I........................................ 20 I Table 7: Fatigue Results for Safe End (60 Years) ........................ ............... 22 I
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| I I
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| I I
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| File No.: VY-16Q-302 Revision: 0 Page 2 of 34 I F0306-OIRO I
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| UStructural IntegrityAssociates, Inc.
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| 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 ............................................................................ I ... 303.....
| |
| 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, Unbolt ....................................... ............................................................. 34 File No.: VY-16Q-302 Page 3 of 34 Revision: 0 F0306-O1 RO
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| V StructuralIntegrityAssociates, Inc.
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| 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 current evaluation so as to achieve a more accurate CUF.
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| U 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
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| StructuralIntegrity Associates, Inc.
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| 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 3 is demonstrated in Figure 2. The input transienttemperature history contains five step-changes of 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.
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| 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.
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| 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.
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| I File No.: VY-16Q-302 Page 5 of 34 Revision: 0 F0306-O1 RO
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| | |
| StructuralIntegrity 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 -
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| counts.
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| 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.
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| The temperatures and pressures for these transients have been modified to account for power uprate
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| [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.
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| 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:
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| I
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| * 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.
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| I
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| * 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.).
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| * Input file "TRANSNT.INP": This file contains the input transient history for all thermal transients to be analyzed forthe location being evaluated.
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| 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.
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| 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.
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| 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.
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| n File No.: VY-16Q-302 Page 6 of.34 Revision: 0 F0306-01 RO
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| I StructuralIntegrity Associates, Inc.
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| 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.
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| 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.
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| 3.1 Transient'Definitions (for program STRESS.EXE)
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| The program. STRESS.EXE requires the following three input files for analyzing an individual transient:
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| * 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..
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| * Green.cfg is configured as described in Reference [5].
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| * 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
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| * 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:
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| o Transients 3, 20, 20A, and 21-23 are run at 25% flow. Although Reference [3]
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| shows 15% flow rate, it is conservative to use 25% flow rate for these transients.
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| 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].
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| o Transient 11 is run at 40% flow.. Transient 1 starts off and ends at 100% flow.
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| o Transients 5, 6, 9, 10, and 19 are run at 100% flow.
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| 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.
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| The results are pulled from the two flow case results based upon the flow rates defined in the thermal cycle diagram [3].
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| 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.
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| 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.
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| File No.: VY-16Q-302 Page 7 of 34 Revision: 0 F0306-O1RO
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| Structural IntegrityAssociates, Inc.
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| 3.2 Peak and Valley Points of the Stress History (for program P-V.EXE)
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| 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.
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| 3.3 Pressure Load The pressure stress associated with a 1000 psi internal pressure was determined in Reference [.1].
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| These values are as follows:
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| Pressure stress for the safe end: I
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| * 8693 psi membrane plus bending stress intensity.
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| * 8891 psi total linearized stress intensity. .
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| Pressure stress for the blend radius:
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| * 36653 psi membrane plus bending stress intensity.
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| * 37733 psi total linearized stress intensity.,
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| 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.
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| The pressure stress is combined with the thermal and piping loads to calculate the final stress values used for fatigue analysis.
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| 3.4 Attached Piping Loads Additionally, the piping stress intensity (stress caused by the attached piping) was determined.
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| These piping forces and moments are determined as shown in Figure 3.
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| U 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 (Mý, =M. - FYL, For Cut I: (MY), = My + FL For Cut Ii: (M,) 2 = MX - FL 2 (My)2 = My + FxL2 File No.: VY-16Q-302 Page 8 of 34 Revision: 0 F0306-O1 RO
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| II Structural IntegrityAssociates, Inc.
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| I The total bending moment and shear loads are obtained using the equations below:
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| I For Cut 1: MX = F(MII)12 +(MY'),,
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| MXY = V(Mx),2 +(My),2 l ~For Cut 11: F . (Fx). 2 ++/-(Fy) 1 2
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| =2 2 2 2 Fx= ý(F) 2 2 ++/-(F). 2 2
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| The distributed loads for a thin-walled cylinder are obtained using the equations below:
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| NZF + Mxy XRN L2 RN irRN[~ 2RNI To determine the primary stresses, PM, due to internal pressure and piping loads, the following i equations are used.
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| For Cut I, using thin-walled equations:
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| I(PM PaN Nz.
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| (E)~=2 tN t N
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| I (pM)o, =PaN tN I (PM)R -P qN TM -
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| 2 SIA_ ((PM)O -(PM)R + (fr.)Z 0
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| - 2 I or Because pressure was considered separately in this analysis, the equations used for Cut I are valid for Cut II.
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| U File No.: VY-16Q-302 Page 9 of 34 Revision: 0 F0306-OI RO
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| StructuralIntegrityAssociates, Inc. .
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| 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.
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| L2= The length from the end of the nozzle where the piping loads are applied to the location of interest in the blend radius.
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| My= The maximum bending moment in the xy plane.
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| Fyx = The maximum shear force in the xy plane.
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| Nz = The normal force per inch of circumference applied to the end of the nozzle in the z direction.
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| qN = The shear force per inch of circumference applied to the nozzle.
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| RN = The mid-wall nozzle radius.
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| Since the pressure was considered separately in this analysis, the equations can be simplified as follows:
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| *(PM.), Nz t
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| (PM)9 =0 (PM)R =0 tN SImx :2(= M )
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| or SIm =2t 71 +(r2 zt0 Per Reference [6], the feedwater nozzle piping loads are as follows:
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| 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 L2 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.
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| 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. The scaled piping stress values File No.: VY-16Q-302 Page 10 of 34 Revision: 0 F0306-O I RO
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| 1 .Structural IntegrityAssociates, Inc.
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| 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.
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| 3.5 Fatigue Analysis (for program FATIGUE.EXE)
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| The number of cycles projected for the 60-year operating life is used for each transient [3]:
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| 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].
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| 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:
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| Blend Radius Safe End Parameters m and. n for 2.0 & 0.2 (low alloy 3.0 & 0.2 (carbon steel)
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| Computing K, steel) [10] [10]
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| Design Stress Intensity 26700 psi [8] @ 600°F 17800 psi [8] @ 600TF Values, Sm.
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| Elastic Modulus from 30.0x106 psi [10] 30.0x106 psi [10]
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| Applicable Fatigue Curve Elastic Modulus Used in Finite Element Model 26.7x 106 psi 28.1xl0 6 psi The Geometric Stress ChGonentrationFacStore1.0 Concentration Factor K, 1.34 [7, page 35 of S4]
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| The results of the fatigue analyses are presented in Tables 6 and 7 for the blend radius and safe end for 60 years, respectively.
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| The results described are contained in EXCEL files BRresults.xls and SEresults.xls, which are contained in the computer files.
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| 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.
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| 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 Page 1I of 34 Revision: 0 F0306-OI RO
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| StructuralIntegrity Associates, Inc.
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| 881-11, 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),
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| | |
| ==Subject:==
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| Evaluation of Request for Relief from NUREG-0619 for VYNPS dated 2/6/95, (TAC No. M88803)).
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| 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.
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| 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%.
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| For the safe end location, the environmental fatigue factors for post-HWC and pre-HWC are all 1.74 from Table 3 of Reference [9]. It results in an EAF adjusted CUF of 1.74 x 0.1471 = 0.2560 for 60 I
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| 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.
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| | |
| ==6.0 REFERENCES==
| |
| : 1. SI Calculation No. VY- 16Q-301, Revision 0, "Feedwater Nozzle Stress History Development for Green Functions."
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| : 2. 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 I
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| 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, 6.
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| "STRESS.EXE, P-V.EXE, and FATIGUE.EXE Software Verification."
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| GE Drawing No. 919D294, Revision 11, Sht. No. 7, "Reactor Vessel," SI File No. VY-05Q-I 241.
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| 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
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| | |
| V StructuralIntegrity Associates, Inc.
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| : 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."
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| : 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.
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| : 12. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section 1.1, Subsection A, Article 4, 1965. Edition with Winter 1966 Addenda.
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| File No.: VY-16Q-302 Page 13 of 34 Revision: 0 F0306-OI RO
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| I C StructuralIntegrityAssociates, Inc.
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| I Table 1: Blend Radius Transients I
| |
| Trwtuiete Timern ,. T 3 $ Plressure Transient Time Temp Time Step Prssure Treestnst. Time Tem Time Step Pressure t0. M Heat.r
| |
| * 14.060V 0 392 I 11 123Cycles 10 70 10 0 80 265_ 90ý 1010 Hlmdmr____ 60 275 6
| |
| . DTestgn 0 70 7OCycles 2650 t80411 I Cycles 6 tOO 90 I
| |
| 100 100 1080 0 WF 10* 20701 302 100O 1010 HF 100 000 100W "Lo l....
| |
| .....
| |
| C.. 5200 100 5000 50
| |
| : 11. Intentf 7070 0
| |
| .. 302 i 302 .
| |
| &000
| |
| .......
| |
| ............1010 1010
| |
| ..... 1.
| |
| .......P-we neducuouteoO%J 500 W00 10
| |
| ................ .010*
| |
| ............ - Ble 0
| |
| M10 392
| |
| -*265 205---
| |
| i-iaa 18
| |
| - "50 * " '*
| |
| j 1010
| |
| '60-a11T ..
| |
| 100 20265 1rdb1010 C 540 16164 _1010 300Cycles 3020 549 3924 < 1010 l................ ... _** ' L .-55" -- ---.- ........... .......
| |
| .
| |
| I
| |
| ..... 1 21164-5491 50* 10*'
| |
| i 35 15*tes 25 t 1135 0025 8920 549 5000 1010
| |
| "*,£%*,-* ~ ~~ ~ ~ T ~ -T ...*- ......
| |
| %..... 0i --........
| |
| ~~ ~~~~T. ~-+' ~ "...".-T
| |
| ~~~~~
| |
| : 4. TurtetRntluo - 549 4 i ! 1010
| |
| .] -' :kL-I*
| |
| ............. 1565.5 *i 66S '" - 20A. Hot Stndby
| |
| =50~~~~
| |
| .
| |
| ..... i+.........
| |
| 549 c.. 100............+1 -.... J1010
| |
| .........
| |
| I 5010
| |
| -b* ....
| |
| and~
| |
| .....
| |
| * .............
| |
| ...... .... ...... 100asdt
| |
| ...
| |
| * 1 11 i* 21M5 2135 50465l 50 440 50 lIi 60 1300
| |
| * 1135*
| |
| 1135 (190toencttnPets i~~~~~i .... ~.........
| |
| - j . ......... -
| |
| .. ..........
| |
| 1002 3u' 20 1 11
| |
| .*--
| |
| ....
| |
| ."........
| |
| i .* so*" " -' ....
| |
| LF21. HF 100 0002 302 5000 W010 .
| |
| ................ ... ...
| |
| ......................
| |
| 1...........
| |
| .... +* + "...-.."_i...
| |
| 1S10415. .r
| |
| + -- - --,600*, : H 1130+... 5451 549 50" 1010 I
| |
| "t. Day 0 392 1010 21423.Shum 1010 5655 505~ 31
| |
| .05 115 M
| |
| Redus-se oe 70 000 1- 270.0 310
| |
| _310 9000 10 .......... ...... . ......
| |
| 3 . . .. ... ... . . . . . . .
| |
| 5oit1 e 11 Cyc 300 828. 4 350 6a04-1 s
| |
| ....Plenty t "t600Lj "Seauu"- " "-i*1500 ..
| |
| HF_10.00 =
| |
| -
| |
| . 302 32 ..
| |
| Soo00 160. .........
| |
| ...........-.-....
| |
| ... " ..... +"'- 546*40.- 18600 ":-_
| |
| l_
| |
| -...00. .....
| |
| 181 .5 1 50 1 113 24. Hyidrestuto 0 100 - 50 64%Pume HFJeelyReO c
| |
| *1800 200 1800 1010 ......... - ... .* - " *102-*-i * -* ' -
| |
| I1 2,000Cycles 00
| |
| - 00 200 392 fool00 1"0 0!O 1010 23.5 z~1405 J t50 50 100 420o j 675 . I Cycles 1200 180l90 T90 100 60 00 i 16 5
| |
| 10400T 02 500 1101 _i2400 10,0 . 00 -r 1 5 5.+Tuntee 0 i:7j47 360 1010 _ 25. UCetut -_ 0- . 15 .
| |
| 27814.5 392 13O . 1010 --- LOBOj100 0 00 2340 205 50 30 1010 I M *0 70 500 HF 100 12. Turbire 0 j 302 1010 3960 ' 26-5 0*8> 1010 Gelerter Trdp 32 .. . '.........V .. T /2375' I
| |
| 4 CyWcl..
| |
| 3420 -0 1010 10400 J 392 N0 1010
| |
| ...._i ' -*90 -*i-?if"6 25 i& -- 160 "ý1M4...
| |
| I 3120 138 4
| |
| : 22. cycl,.- 3210 2 31 4 101 9591 302 1530010 J 1010 Note: I. The indicatedtime orpressure was assumed
| |
| : 2. 1375 psi is for Transient 13 only.
| |
| Table 2: Safe End Transient Trerslellt
| |
| . .umber.
| |
| Time Temp
| |
| .
| |
| Time Step
| |
| .
| |
| Pressure
| |
| . .
| |
| Transiet
| |
| .......
| |
| Time Temp imeStep Pressure Transient Time TimeStp PresurM lTemp I
| |
| * 26 50 0 loio 3 CyI 10 70 t0 I 60 775 i 6 1890 260 000o 1010 HFI100 i==y == 960 10too 900 . 50 2570 302 S00 1010. HF 100 14.0 1' 0 - - .
| |
| .. Si6"r*.......
| |
| Test.r.
| |
| 1"'M
| |
| .......
| |
| 100 1000 0 7 18. RednuO to 0% 1 0 392 1010 1I. tOS. ot 0 i 392 1010 ib2 "
| |
| ....... 26"5 1800- 1010*
| |
| HF...*.... 108 F 10
| |
| . H.. .
| |
| 16i0 1150 54 . 10 5280 150 300
| |
| ~ ~ ~~
| |
| I 10 ... 55 . 25 1....
| |
| 1
| |
| : 20. 0 6 i 4, 1010
| |
| _o~*,dy 6380 100 500 5 I 440 1 w01
| |
| : 3. Slarbtp 0 'O0 , 56 13.5 i 50 9 1135 .
| |
| ...300Cycles 2.. 3925 4420'-- .' - 549 54-9"'* 3924 S
| |
| 50-0 ' 1010 1010 ...
| |
| 145 50 1.71 1135 tFO2 16664 . 549 500 1010. 20. Hot Standby 0 540 1010 4.TrlnRoll 182 ....... .....
| |
| .55.5.565 FW j6ecton Portion] 1W 1010 1801... 1....
| |
| : 00. _..+....... ............ -.... 1 .....
| |
| .andlc..n..... 2165.5 565 600 1135 O8Cycles 181 100 _1600 . " ....
| |
| I 1F129
| |
| .... 1. 21 : " - 54""+
| |
| 2909+
| |
| t0nted 21605050 210 1010 1210 1*5*00 41 549 500. . 010 547ý5 . 565 1 15 3754 6264 5010 Redcons 0_Iy 9006 *310 392 900 4 11 1010R, 6775 505 132 1135 2-309
| |
| .... F..
| |
| Cylshdo 2.5.... .
| |
| *20
| |
| .. -- 33~ ' 60 50 75% P~mm -. 2700 310 - i I 7148.5 50 42 675 15144 100 82800 5 I
| |
| 22.
| |
| * 145 . 39 50 1010 .
| |
| 10-10'-*i 11048530 67 H8.800C 41u0300 392 900 1010 TClest 100 100 600 1563 5 W + klyRduce 8 :*1OlO 164125549 1 1010 1800 i 100 8000 50
| |
| -29 IWOn.& 200 low80 1010 -18,21.25' 591.0 11 18213 100 100 24 1 00 600 50 HF10 5400 392 18oo 1010 20213:5 1 100 18000 10 I
| |
| : 0. Turbnee
| |
| ...i :T_ I0:'!4i 1 ; -"-61010..-. .... 200)145 2 7 1 '101 21814.5 392 180 01 1560 70 o00 0 2340 80 300 1010 10 Cyc.es 12. Torbine 10 32 5 1101010 0100 342D 265 900 U. 1010
| |
| .260...,. . .-. ... 1010..
| |
| 90 275 00 540 54900 302 100 1010 5900G. SOO50 1.10 228cyclre 2750 10 82 HF_100 2791 3210 4991 S0o1 26094 251 392 5"2-41" 1381 500 1010 1010 1010 "
| |
| I 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 transientsin Table I areplotted using a 5000 second steady state increment. The difference is due to the length of the Green's Functionfor the safe end which is shorter compared to the blend Radius.
| |
| I 0 2. The indicatedtime or pressurewas assumed VY-16Q-302
| |
| : 3. 1375 psi isfor Transient 13 only.
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| No.: 1 File File No.: VY-16Q-302 Revision: Page 14 of 34 I Revision: 0 F0306-OI RO
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| | |
| V StructuralIntegrityAssociates, Inc.
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| Table 3: Maximum Piping Stress Intensity Calculations Safe End External Pioina Loads Blend Radius External Piping Loads Parameters Parameters Fx 3.00 kips Fx = 3.00 kips Fy 15.00 kips. Fv= 15.00 kips Fz 3.20 kips Fz 3.20 kips MX_= .336.00 in-kips MX= 336.00 in-kips my= 156.00 -in-kips my = 156.00 in-kips Mz= 480.00 in-kips Mz 480.00 in-kips OD= 11.86 in OD= 22.67 in ID= 10.409 in 1D= 10.750 in RN = 5.57 in RN= 8.35 in L= 12.09 in L= 27.57 in tN = 0.72 in tN= 5.96 in (M) = 154.69 in-kips (Mx)2 = -77.58 in-kips M = 192.26 in-kips S(M1)2 = 238.72. in-kips MXY 246.77 in-kips M* = 251.01 in-kips Fxv= 15.30 kips Fxy = 15.30 kips Nz= 2.63 kips/in Nz= 1.21 kips/in qN -1.59 kips/in qN = -0.51 kips/in Primary Membrane Stress Intensity Primary Membrane Stress Intensity
| |
| * PMz 3.63 ksi PMz 0.20 ksi
| |
| = -2.20 ksi T = -0.09 ksi Slmax 5.71 ksi Slmax= 0.27 ksi Slmax 5707.97 psi Slmax = 265.47 psi Note: The locations for Cut I and.Cut II were defined in Reference [1] for safe end and blend radius paths, respectively.
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| File No.: VY-16Q-302 Page 15 of 34 Revision: 0 F0306-0 IRO
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| | |
| StructuralIntegrityAssociates, Inc. U Table 4: 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+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 33609.73 300 O
| |
| 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
| |
| ____0 7720 7720 6752 672 392 392 1010 1010 38110.33 38110.33 37019.53 37019.53 169.2692 169.2692 169.2692 169.2692 45999.60 45999.60 43940.80 43940.80 10000 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 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 1 14 59600 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 15.77042 15.77042 15.77 15.77 123 25 1580 0 0 70 00 ! 0 15.7 461 0 0 0.00 0.00 123 File No.: VY-16Q-302 Page 16 of 34 Revision: 0 F0306-01 RO I
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| | |
| UStructural IntegrityAssociates, 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.
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| 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°F)/(575°F -70°F).
| |
| Column 10: Same as Column 9, but for M+B stress.
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| Column 11: Sum of total stresses(Columns 3, 7, and 9).
| |
| Column 12: Sum of membrane plus bending stresses (Columns 4, 8, and 10).
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| Column 13: Number of cycles for the transient (60 years).
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| File No.: -VY-16Q-302 Page 17 of 34 Revision: 0 F0306-01 RO
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| | |
| StructuralIntegrity Associates, Inc. a Table 5: Safe End Stress Summary I
| |
| 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+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
| |
| 2 1680 6960 0
| |
| 0 0
| |
| 0 0
| |
| 0 0
| |
| 0 0
| |
| 0 70 70 100 100 0
| |
| 0, 1100 50 00 0.
| |
| 9780.1 444.55 0
| |
| 0 0 9562.3 339.0875 339.0875 434.65 339.0875 339.0875 0
| |
| 0 0.00 0.00 10119.19 783.64 0.00 0.00 9901.39 773.74 123 120 1201 120 I
| |
| 0 -170 -165 100 50 444.55 434.65 -339.0875 -339.0875 -64.54 -69.44 300 153.2 16328.2 16664
| |
| -235 2
| |
| -1
| |
| -212 3
| |
| 0 104.256 549 549 50 444.55 1010 -8979.91 1010 8979.91 434.65 -387.1927 -387.1927 8779.93 5414.097 5414.097 8779.93 -5414.097 5414.097
| |
| -177.64 14396.01 3564.81
| |
| -164.54 14197.03 14194:03 300 300 300 I
| |
| 0 -3 -2 '549 1010 8979.91 8779.93 -5414.097 -5414.097 3562.81 3363.83 300 I
| |
| 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
| |
| F 3600 3684.4
| |
| -4100 0
| |
| -169 33 22 22
| |
| -110 35 23 23 392 392 392
| |
| .392
| |
| . 1010 1010
| |
| .1010 1010 8979.91 8979.91 8979.91 8979.91 8779.93 -3639.539 -3639.539 8779.93 3639.539 3639.539 8779.93 3639.539 3639.539 8779.93 3639.539 3639.539 5171.37 12652.45 12641.45 12641.45 5030.39 12454.47 12442.47 12442.47 10000 10000 10000 2000 I
| |
| 1800.1 196 159 280 1010 8979.91 8779.93 2373.612 2373.612 11549.52 11312.54 2000 6 5400.2 5496.6 5900
| |
| -108 29 22
| |
| -68 31 23 392 392 392 1010 1010 1010 8979.91 8979.91 8979.91 8779.93 -3639.539 -3639.539 8779.93 3639.539 3639.539 8779.93 3639.539 3639.539 5232.37 12648.45 12641.45 5072.39 12450.47 12442.47 2000 2000 2000 I
| |
| 0 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 10 I
| |
| 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 5470.6 5900 0
| |
| -126 31 22 23
| |
| -80 "
| |
| 32 23 22 392 392 392 392 1010 1010 1010 1010 8979.91 8979.91 8979.91 8979.91 8779.93 -3639.539 -3639.539 8779.93 3639.539 3639.539 8779.93 3639.539 3639.539 8779.93 3639.539 3639.539 5214.37 12650.45 12641.45 12642.45 5060.39 12451.47 12442.47 12441.47 10 10 10 70 U
| |
| 77.1 2308 3188 285.461 1010 8979.91 8779.93 2435.338 2435.338 13723.25 14403.27 70 10 169.4 1890 1968.2
| |
| -12
| |
| -1069 74
| |
| -13 72
| |
| -1511 265 265 322.362 1010 1010 1010 8979.91 8979.91 8979.91 8779.93 -2204.069 -2204.069 8779.93 2204.069 2204.069 8779.93 -2852.427 -2852.427.
| |
| 6763.84 11257.98 5058.48 6562.86 11056.00 4416.50 70 70 70 I
| |
| 2147.2 91 90 392 1010 8979.91 8779.93 3639.539 3639.539 12710.45 12509.47 70 I
| |
| 2570 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 70 0 -29 -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 11 2168.4 6730.4 7243.2 60377 41773 5409.4 -14924 -10329 60377 41773
| |
| -1965 .- 1434 565 128.917 50 50
| |
| '1134 10082.39 9857.862 -226.0583 -226.0583 1054 9371.114 9162.422 -5594.944 -5594.944 1133 10073.5 9849.169 -226.0583 -226.0583 675 6001.425 5867.775 -665.9339 -665.9339 70233.34
| |
| -11147.83 70224.44 3370.49 51404.80
| |
| -6761.52 51396.11 3767.84 10 10 10 10 I
| |
| 18215.4 52636 36417 . 100 1010 8979.91 8779.93 339.0875 339.0875 61955.00 45536.02 10 20015.5 -24511 -16189 22314.5 0
| |
| 22 23 23 22 260.183 392 392 1010 8979.91 8779.93 -2149.623 -2149.623 937 8330.867 8145.341 3639.539 3639.539 1010 8979.91 8779.93 3639.539 3639.539
| |
| -17680.71 11992.41 12642.45
| |
| -9558.69 11807.88 12441.47 10 10 60 I
| |
| 10 23 22 392 1135 10091:29 9866.555 3639.539 3639.539 13753.82 . 13528.09 60 I
| |
| 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 30 90 3174 23 23 2793.5 -16189 -24511 22 22 4383
| |
| . 392 392 275 260.183 1375 12225.13 11952.88 3639.539 3639.539 940 940 8357.54 8357.54 8171.42 3639.539 3639.539 8171.42 2317.098 2317.098 941 8366.431 8180.113 -2149.623 -2149.623 15887.66 12020.08 13848.64
| |
| -9972.19 15614.41 11832.96 1487,1.52
| |
| -18480.51
| |
| _1, 1
| |
| 1 1
| |
| I
| |
| . 5091 23 22i 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 1 I
| |
| File No.: VY-16Q-302 Revision: 0 Page 18 of 34 I F0306-OI RO I
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| | |
| V StructuralIntegrity 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 (psiR psi) F (osil) (pspsi) fps ps 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 -2 -1 549 1010 8979.91 8779.93 -5414.097 -5414.097 3563.81 3364.83 300 0 -3 -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 -3 -2 549 1010 8979.91 8779.93 -5414.097. -5414.097 3562.81 3363.83 300 0 -3 -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 -5 -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 01 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: 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 2.
| |
| Column 7: Total pressure stress intensity from the quantity (Column 6 x 8891)/1000 [Table 3, 11.
| |
| Column 8: Membrane plus bending pressurestress intensity from the quantity (Column 6 x 8693)/1000
| |
| [Table3, f].
| |
| Column 9: Total external stress from calculation in Table 3, 5707.97 psi*(dolumn 5-70°F)/(575°F -70°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 (Columns 4, 8, and 10).
| |
| Column 13 Number of cycles for the transient (60 years).
| |
| File No.: VY-16Q-302 Page 19 of 34 Revision: 0 F0306-01 RO
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| | |
| StructuralIntegrity Associates, Inc. I Table 6: Fatigue Results for Blend Radius (60 Years) I LOCATION = LOCATION NO. 2 -- BLEND RADIUS FATIGUE CURVE = 1 (1 = CARBON/LOW ALLOY, m =2.0 n= .2 2 = STAINLESS STEEL)
| |
| I Ecurve Sm = 26700. psi 3.OOOE+07 psi Eanalysis = 2.670E+07 psi I
| |
| Kt = 1.00 MAX MIN RANGE MEM+BEND Ke Salt Napplied Nallowed UI 74568. 0. 74568. 62689. 41892.. 1000E+01 7.488E+03 I
| |
| 1.000 .0013 70231. 0. 70231. 58499. 1 000 39456. 1. OOOE+01 8. 944E+03 .0011 69395. 0. 69395. 59106. 1.000 38986. 1.OOOE+01 9.2 68E+03 .0011 67667. 0. 67667. 59377. 1.000 38015. 9. 300E+01 9. 988E+03 .00.93 67667.
| |
| 67667.
| |
| 67282.
| |
| 0.
| |
| 0.
| |
| 0.
| |
| 67667.
| |
| 67667.
| |
| 67282.
| |
| 59377.
| |
| 59377.
| |
| 60118.
| |
| 1.000 1.000 1.000 38015.
| |
| 38015.
| |
| 37799.
| |
| 1.200E+02
| |
| .8. 700E+01 1.OOOE+01
| |
| : 9. 988E+03
| |
| : 9. 988E+03
| |
| : 1. 018E+04
| |
| .0120
| |
| .0087
| |
| .0010 I
| |
| 67142. 0. 67142. 60462. 1.000 37720. 1.OOOE+01 1.025E+04 .0010 66791.
| |
| 66791.
| |
| 66791.
| |
| 0.
| |
| 0.
| |
| 16.
| |
| 66791.
| |
| 66791.
| |
| 66775.
| |
| 62353.
| |
| 62353.
| |
| 62337.
| |
| 1.000 1.000 1.000 37523.
| |
| 37523.
| |
| 37514.
| |
| : 1. OOOE+00
| |
| : 1. 500E+01 1.230E+02 1.044E+04 1.044E+04
| |
| : 1. 045E+04
| |
| .0001
| |
| .0014
| |
| .0118 I
| |
| 66791.
| |
| 66298.
| |
| 66298.
| |
| 1902.
| |
| 1902.
| |
| 1902.
| |
| 64889.
| |
| 64396.
| |
| 64396.
| |
| 60505.
| |
| 47410.
| |
| 47410.
| |
| 1.000 1.000
| |
| .1.000 36454.
| |
| 36177.
| |
| 36177.
| |
| 9.OOOE+01 3.000E+01
| |
| : 1. OOOE+00
| |
| : 1. 152E+04
| |
| : 1. 182E+04 1.182E+04
| |
| .0078
| |
| .0025
| |
| .0001 I
| |
| 66298. 1902. 64396. 47410. 1.000 36177. 1. OOOE+00 1. 182E+04 .0001 66298.
| |
| 66298.
| |
| 64150.
| |
| 30389.
| |
| 31068.
| |
| 31068.
| |
| 35909.
| |
| 35230.
| |
| 33081.
| |
| 21760.
| |
| 23734.
| |
| 34263.
| |
| 1.000 1.000 1.000 20173.
| |
| 19792.
| |
| 18585.
| |
| 1.OOOE+00
| |
| : 2. 670E+02 3.300E+01
| |
| : 9. 581E+04 1.038E+05
| |
| : 1. 303E+05
| |
| .0000
| |
| .0026
| |
| .0003 I
| |
| 64150. 31070. 33079. 34283. 1.000 18584. 2.700E+01 1.303E+05 .0002 59772.
| |
| 58992.
| |
| 31070.
| |
| 31070.
| |
| 31070.
| |
| 28702.
| |
| 27922.
| |
| 31815.
| |
| 31800.
| |
| 1.000 1.000 16125.
| |
| 15687.
| |
| 1.OOOE+00
| |
| : 1. OOOE+00
| |
| : 22. 222E+05 2 519E+05
| |
| .0000 0000 U
| |
| 55364. 24293. 25433. 1.000 13648. 2 .710E+02 4. 757E+05 .0006 55364.
| |
| 55364.
| |
| 55364.
| |
| 31682.
| |
| 32964.
| |
| 34282.
| |
| 23681.
| |
| 22400.
| |
| 21082.
| |
| 17402.
| |
| 17300.
| |
| 17307.
| |
| 1.000 1.000 1.000 13304.
| |
| 12584.
| |
| 11844.
| |
| : 1. OOOE+01 1.OOOE+01
| |
| : 9. OOE+00
| |
| : 5. 703E+05 9.414E+05
| |
| : 1. 912E+06
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 55042. 34282. 20761. 18195. 1.000 11663. 7 . OOOE+01 2. 231E+06 .0000 54965.
| |
| *54965.
| |
| 54965.
| |
| 34282.
| |
| 34317.
| |
| 34327.
| |
| 20683.
| |
| 20648.
| |
| 20638.
| |
| 18463.
| |
| 18464.
| |
| 18463.
| |
| 1.000 1.000 1.000 11620.
| |
| 11600.
| |
| 11595.
| |
| 2.210E+02
| |
| : 1. OOOE+01 6.900E+01
| |
| : 2. 310E+06 2.348E+06
| |
| : 2. 358E+06
| |
| .0001
| |
| .0000
| |
| .0000 I
| |
| 53963.
| |
| 53963.
| |
| 53963.
| |
| 34327.
| |
| 34328.
| |
| 34329.
| |
| 19637.
| |
| 19636.
| |
| 19635.
| |
| 17393.
| |
| 17401.
| |
| 17413.
| |
| 1.000 1.000 1.000 11032.
| |
| 11031.
| |
| 11031.
| |
| : 2. 310E+02
| |
| : 3. OOOE+02
| |
| : 3. OOOE+02 3.757E+06 3.-758E+06 3.760E+06
| |
| .0001
| |
| .0001
| |
| .0001 I
| |
| 53963. 34329. 19635. 17413. 1.000 11031. 3. OOOE+02 3.760E+06 .0001.
| |
| 53963.
| |
| 53963.
| |
| 53963.
| |
| 34329.
| |
| 34329.
| |
| 41522.
| |
| 19635.
| |
| 19635.
| |
| 12441.
| |
| 17413.
| |
| 17413.
| |
| 10688.
| |
| 1.000 1.000 1.000 11031.
| |
| 11031.
| |
| 6989.
| |
| 3.OOOE+02
| |
| : 3. 0OOE+02 1.200E+02
| |
| : 3. 760E+06
| |
| : 3. 760E+06
| |
| : 1. OOOE+20
| |
| .0001
| |
| .0001
| |
| .oo0o I
| |
| 53963.
| |
| 53963.
| |
| 53963.
| |
| 43358.
| |
| 43358.
| |
| 43358.
| |
| 10605.
| |
| 10605.
| |
| 10605.
| |
| 9647.
| |
| 9.647.
| |
| 9647.
| |
| 1.000 1.000 1.000 5958..
| |
| 5958.
| |
| 5958.
| |
| : 6. OOOE+01 1.OOOE+00 8.800E+01 1.OOOE+20
| |
| : 1. OOOE+20 1.OOOE+20
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 51835. 43358. 8477. 7712 1.000 4762. 1. 400E+02 1.000E+20 .0000 51835.
| |
| 51835.
| |
| 51782.
| |
| 46000.
| |
| 46000.
| |
| 46000.
| |
| 5835.
| |
| 5835.
| |
| 5783.
| |
| 5149.
| |
| 5146.
| |
| 6568.
| |
| 1.000 1.000 1.000 3278.
| |
| 3278.
| |
| 3249.
| |
| : 3. OOOE+02
| |
| : 9. 560E+03
| |
| : 1. OOOE+01 1.000E+20
| |
| : 1. OOOE+20
| |
| : 1. OOOE+20
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| File No.: VY-16Q-302 Revision: 0 Page 20 of 34 I F0306-0IRO I
| |
| | |
| V Structural IntegritvAssociates, Inc.
| |
| I -, A Aq1
| |
| *nn C AQ1 ; r 1 1 9 1.000 2761. 1. 00.OE+01 1. OOOE+20 .0000 50716. 46000. 4717. 4582. 1.000 2650. 6. OOOE+01 1. OOOE+20 .0000 50716. 46000. 4717. 4582. 1.000 2650. 2.280E+02 1.00OE+20 .0000 46000. 46000. 0. 0. 1.000 0. 1. 320E+02 1.OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 1. OOOE+04 1.OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 2. OOOE+03 1.OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 2. OOOE+03 1. OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 1.OOOE+01 1.OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 1. OOOE+01 1.OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 7. OOOE+01 1.OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 7.OOOE+01 1.OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 1.OOOE+01 1.OOOE+20 .0000 46000. 46000. .0. 0. 1.000 0. 1. OOOE+01 1.OOOE+/-20 .0000 46000. 46000. 0. 0. 1.000 0. 6. OOOE+01 1. OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 6. OOOE+01 1.000E+20 .0000 46000. 46000. 0. 0. 1.000 0. 1. OOOE+00 1.OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 1. OOOE+00 1. OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 1. OOOE+00 1.OOOE+20 .0000 46000. 46000. 0. 0. 1.000. 0. 2. 280E+02 1.OOOE+20 .0000 46000. 46000. 0. 0. 1.000 0. 2.. 280E+02 1.OOOE+20 .0000 TOTAL USAGE FACTOR = .0636 File No.: VY-16Q-302 Page 21 of 34 Revision: 0 F0306-01 RO
| |
| | |
| Structural IntegrityAssociates, Inc. I Table 7: Fatigue Results for Safe End (60 Years)
| |
| I I
| |
| LOCATION = LOCATION NO. 1 SAFE END FATIGUE CURVE = 1 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL) m = 3.0 n= .2 Sm = 17800.
| |
| Ecurve = 3.000E+07 psi Eanalysis = 2.810E+07 psi psi I
| |
| Kt = 1.34 MAX MIN RANGE MEM+BEND Ke Salt Napplied Nallowed U I
| |
| :70233.
| |
| 70224.
| |
| 61955.
| |
| -17681.
| |
| -15714.
| |
| -12491.
| |
| 87914.
| |
| 85938.
| |
| 74446.
| |
| 60963.
| |
| 60879.
| |
| 53128.
| |
| 1.283 1.280 1.000 74422.
| |
| 72869.
| |
| 49383.
| |
| 1.OOOE+01 1.OOOE+01 1.000E+01 1.338E+03 1.415E+03
| |
| : 4. 568E+03
| |
| .0075
| |
| .0071
| |
| .0022 I
| |
| 58867. -12491. 71359. 52938. 1.000 47700. 1. OOOE+01 5. 094E+03 .0020 53379.
| |
| 53379.
| |
| 53379.
| |
| -12491.
| |
| -11148.
| |
| -10720.
| |
| 65870.
| |
| 64527.
| |
| 64099.
| |
| 47699.
| |
| 46869.
| |
| 46361.
| |
| 1.000 1.000 43819.
| |
| 42951.
| |
| : 2. 800E+02 1.000E+01
| |
| : 6. 552E+03 6.953E+03
| |
| .0427
| |
| .0014 I
| |
| 1.000 42631. 1. OOOE+01 7. 109E+03 .0014 53379.
| |
| 53379.
| |
| 53379.
| |
| -9972.
| |
| -9972.
| |
| -9972.
| |
| 63351.
| |
| 63351.
| |
| 63351.
| |
| 58588.
| |
| 58588.
| |
| 58588.
| |
| 1.194 1.194 1.194 53087.
| |
| 53087.
| |
| 53087.
| |
| 6.OOOE+01 1.
| |
| IOOE+00 2.280E+02
| |
| : 3. 628E+03
| |
| : 3. 628E+03
| |
| : 3. 628E+03
| |
| .0165
| |
| .0003
| |
| .0628 I
| |
| 53379. -9060. 62439. 44702. 1.000 41444. 1. 100E+01 7.731E+03 .0014
| |
| .15888.
| |
| 14569.
| |
| 14522.
| |
| -9060.
| |
| -9060.
| |
| -9060.
| |
| 24948.
| |
| 23629.
| |
| 23582.
| |
| 20209.
| |
| 17779.
| |
| 18921.
| |
| 1.000 1.000 1.000 16985.
| |
| 15840.
| |
| 16022.
| |
| : 1. OOOE+00
| |
| : 1. 000E+00 2.870E+02 1.802E+05
| |
| : 2. 410E+05 2.287E+05
| |
| .0000
| |
| .0000 0013 I
| |
| 14522. -3008.
| |
| U 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.
| |
| 14226.
| |
| 13849.
| |
| -971.
| |
| -178.
| |
| -178.
| |
| 15196.
| |
| 14404.
| |
| 14026.
| |
| 13248.
| |
| 14178.
| |
| 15036.
| |
| 1.000 1.000 1.000 10516.
| |
| 10262.
| |
| 10216.
| |
| : 2. 860E+02 1.400E+01
| |
| : 6. OOOE+01
| |
| : 5. 531E+06
| |
| : 6. 379E+06
| |
| : 6. 547E+06
| |
| .0001
| |
| .0000
| |
| .0000 U
| |
| 1384 9. -178. 14026. 15036. 1.000 10216. 1. OOOE+00 6. 547E+06 .0000 13849.
| |
| 13849.
| |
| -178.
| |
| -68.
| |
| 14026.
| |
| 13916.
| |
| 13821.
| |
| 15036..
| |
| 14943.
| |
| 1.000 1.000 10216.
| |
| 10141.
| |
| : 2. 250E+02
| |
| : 3. OOOE+00
| |
| : 6. 547E+06
| |
| : 6. 837E+06
| |
| .0000
| |
| .0000 I
| |
| 13754. -68. 13600. 1.000 9846. 6. OOOE+01 8. 117E+06 .0000 13754.
| |
| 13723.
| |
| 13723.
| |
| -68.
| |
| -68.
| |
| -65.
| |
| 13821.
| |
| 13791.
| |
| .13788.
| |
| 13600.
| |
| 14475.
| |
| 14473.
| |
| 1.000 1.000 1.000 9846.
| |
| 9.989.
| |
| 9987.
| |
| 2.280E+02
| |
| : 9. OOOE+00 6.100E+01
| |
| : 8. 117E+06 7 .465E+06 7.474E+06
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 12722. -65. 12786. 12548. 1.000 9103. 1.OOOE+01 1.729E+07 .0000 12710.
| |
| 12652.
| |
| 12652.
| |
| -65.
| |
| -65.
| |
| 0.
| |
| 12775.
| |
| 12717.
| |
| 12652.
| |
| 12579.
| |
| 12524.
| |
| 12454.
| |
| 1.000 1.000 1.000 9102.
| |
| 9061.
| |
| 9014.
| |
| : 7. OOOE+01 1 590E+02 1.230E+02 1.730E+07
| |
| : 1. 833E+07
| |
| : 1. 959E+07
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 12652.
| |
| 12652.
| |
| 12652.
| |
| 0.
| |
| 0.
| |
| 339.
| |
| 12652.
| |
| 12652.
| |
| 12313.
| |
| 12454.
| |
| 12454.
| |
| 12115.
| |
| 1.000 1.000 1.000 9014.
| |
| 9014.
| |
| 8772.
| |
| : 1. 200E+02
| |
| : 1. 230E+02
| |
| : 1. 230E+02
| |
| : 1. 959E+07
| |
| : 1. 959E+07
| |
| : 2. 905E+07
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 12652. 784. 11869. 11681. 1.000 8456. 1. 200E+02 4. 952Et07 .0000 12652.
| |
| 12652.
| |
| 12652.
| |
| 784.
| |
| 784.
| |
| 921.
| |
| 11869.
| |
| 11869.
| |
| 11732.
| |
| 11681.
| |
| 11681.
| |
| 11542.
| |
| 1.000 1.000 1.000 8456.
| |
| 8456.
| |
| 8357.
| |
| : 1. OOOE+00
| |
| : 1. OOOE+00
| |
| : 1. OOOE+00 4 . 952E+07
| |
| : 4. 952E+07 5.4 62E+07 0000
| |
| .0000
| |
| .0000 I
| |
| 12652. 1328. 11325.
| |
| I 11257. 1.000 8088. 1.OOOE+00 7. 100E+07 .0000 12652. 3370. 9282. 8687. 1.000 6531. 1000E+01 1.OOOE+20 .0000 12652. 3563. 9090. 9091. 1.000 6502. 3.OOOE+02 1.OOOE+20 .0000 12652. 3563. 9090. 9091. 1.000 6502. 3. OOOE+02 1. OOOE+20 .0000 File No.: VY-16Q-302 Revision: 0 Page 22 of 34 I F0306-01RO I
| |
| | |
| H StructuralIntegrity Associates, Inc.
| |
| 12652. 3563. 9090. 9091. 1.000 6502. 3. OOOE+02 1.000E+20 .0000 12652. 3563. 9090. 9091. 1.000 6502. 3. OOE+02 1.OOOE+20 .0000 12652. 3564. 9089. 9090. 1.000 6501. 3.OOOE+02 1.OOOE+20 .0000 12652. 3565. 9088. -1740. 1.000 4535 3. OOOE+02 1. OOOE+20 .0000 12652. 3896. 8756. 8613. 1.000 6237. .3.OOOE+02 1.000E+20 .0000 12652. 5058. 7594. 8038. 1.000 5513. 7. 000E+01 1.OOOE+20 .0000 12652. 5171. 7481. 7424. 1.0oo 5341. 7.048E+03 1. OOOE+20 .0000 12650. 5171. 7479. 7421. 1.000 5339. 1.OOOE+01 1. OOOE+20 .0000 12648. 5171. *2.0OOE+03 7477. 7420. 1.000 5338. 1.000E+20 12642. 5171. 7471. 7411. 1.000 5333. 7.OOOE+01 1. OOOE+20 .0000 12642. 5171. 7471. 7411. 1.000 5333. 7. 000E+01 1.000E+20 .0000 12642. 5171. 7471. 7411. 1.000 5333. 6. OOOE+01 1. OOOE+20 .oooo
| |
| .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. 00OE+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 1.006E+20 .0000 12641. 5214. 7427. 7382. 53.04. 1.OOOE+01 1.OOOE+20 .0000 12641. 5232. 7409. 7370. 1.000 1 .00.0 5293. 2. OOOE+03 1. OOOE+20 ..0000 12641. 5311. 7330. 7329. 1.000 5243. 1. 000E+0.1 1. OOOE+20 .0000 12641. 6442. 6200. 6078. 1.000 4412. 1.OOOE+01 1. OOOE+20 .0000 12641. 6667. 5975. 5972. 1.000 4273. 3.OOOE+02 1. OOOE+20 6764. 4.205. .0000 12641. 5878. 5880. 1.000 7.000 E+01 1. OOOE+20 12641. 9690. 1.000 1. OOOE+00 .0000 2951. 3031. 2126. 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.OOOE+01 1.OOOE+20
| |
| .0000 12641. 11256. 1385. 1384. 1.000 991. 3. OOOE+02 1.060E+20
| |
| -.0000 12641. 11258. 1383. 1386. 1.000 990. 7. OOOE+01 1.OOOE+20 .00ooo 12641. 11281. 1360. 1360. 1.000 973. 1.OOOE+01 1.OOOE+20 12641. 11403. .0000 1238. 1281. 1.000 894. 3. OOOE+02 1. 000OE+20 12641. 11550. 1130. 1.000 .0000 1092. 788. 2. OOOE+03 1. OOOE+20 12641. 11911. .0000 731. 1034. 1.000 578. 1.OOOE+01 1.OOOE+20 12641. 11937. .0000 705. 761. 1.000 514. 4. 555E+03 1. OOOE+20 12641. 11937. 705. 1.000 .0000 761. 514. 5. 445E+03 1.OOOE+20 12641. 11992. .0000 649. 635. 1.000 462. 1. OOOE+01 1. OOOE+/-20 1264 1. 12020. 621. .0000 610. 1.000 442. 6. OOOE+01 1.OOOE+20 12641. .0000 12020. 621. 610. 1.000 442. 1. OOOE+00 1. OOOE+20
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| .0000 12641. 12020. 621. 610. 1.000 442. 2.280E+02 1.OOOE+20 12641. 12640. .0000
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| : 1. 0. 1.000 1. 3. OOOE+02 1. OOOE+20 12641. .0000 12641. 0. 0. 1.000 0. 3. 956E+03 1.000E+20 1264 1. .0000 12641. 0. 0. 1.000 1.000O 0. 2. OOOE+03 1.OOOE+20 12641. 12641. 1.000 .0000,
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| : 0. 0. 1.000 0. 2. 000E+03 1.OOOE+20 12641. 12641. 1.000 0. .0000
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| : 0. 0. 1.OOOE+01 1. OOOE+20 12641. .0000 12641. 0. 0. 0. 1. OOOE+01 1.OOOE+20 12641. 12641. .0000
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| : 0. 0. 0." 1. OOOE+00 1. OOOE+20 TOTAL USAGE FACTOR .1471 File No.: VY-16Q-302 Page 23 of 34 Revision: 0 F030601 RO
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| ! StructuralIntegrityAssociates, Inc.
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| 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). I Figure 1: Typical Green's Functions for Thermal Transient Stress I
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| I File No.: VY-16Q-302 Page 24 of 34 Revision: 0 F0306-O1RO
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| V Structural IntegrityAssociates, Inc.
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| ýWýn I . - I .
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| +SOS,
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| -2ý5 Skp 1-15 SkP
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| . IIlllll 200 .
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| Is1%n.
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| 02400 4W6080r10400 - W IAK180 IBMZOW Tbminss 15 ,i*,.
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| SJI
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| ....S i i:' ii : !:* i 6.=
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| 0- . "
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| -41
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| -6O 0! 20 .400 600 8$0 10001200 140 1600 1r*M. ?N Tbm.,.w Figure 2: Typical Stress Response Using Green's Functions File No.: VY-16Q-302 Page 25 of 34 Revision: 0 F0306-O I RO
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| StructuralIntegrityAssociates, Inc. I Fj Figure 3: External Forces and Moments on the Feedwater Nozzle
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| [- Temp (°) - - Pressure (psig) 60 1 70 60 50 0.
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| , 40.
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| 4, 0.
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| 30 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.
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| The chosen length of 10 seconds has no significance 20 - as there is no temperature change during this transient.
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| 10-0- -1 0 1 2 3 4 5 6 7 8 9 10 Time (seconds)
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| Figure 4: Transient 1, Bolt-up File No.: VY-16Q-302 Page 26 of 34 Revision: 0 F0306-O1 RO
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| I StructuralIntegrityAssociates, Inc.
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| 17Temp CT) - - pressure (psig)l 120 1200 I I
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| *100 8O a
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| E 40 20 1000 2000 3000 4000 5000 6000 Time (seconds)
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| Figure 5: Transient 2, Design HYD Test
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| - Temp ('F) -Pressure (psig) 600 - 1080 1040 300 E a I8 5000 10000 15000 20000 Time (seconds)
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| Figure 6: Transient 3, Startup File No.: VY-16Q-302 Page 27 of 34 Revision: 0 F0306-OI RO
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| V StructuralIntegrityAssociates, Inc.
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| I 600.
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| -ýTemp VF)--Prsrepsg I I--Temp ('F) m -Pressure (psig) ] 1080 I
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| 1040 1000 S.t'ess.exe program 960 automatically calculates steady 920 500 stale conditions at beginning 880 of transients. This transient 1 I
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| begins at 549*F and steps 840 Idown to 100F in one second. 800 760 400 720
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| -680 I
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| -640
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| -600 560 300 emperature of 392'F is held -520 E for 5000 seconds so that steady 480 I
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| 2- state is reached. That way, this 440 I-transient will match up with the 400 200 Temperature of 100"F is held following one which will start off long enough so that steady state at a steady state of 392°F. No 360 is reached. It is conservatively length of time for the 392"F 320 assumed that steady state is 280 value is specfied on the reached before the next I
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| I thermal cycle diagrams, so 240 temperature spike occurs.
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| steady state conditions were 200 100 .f- assumed. -
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| 160 120 80 I
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| 40 0 a 0 1000 2000 3000 4000 5000 6000 7000 8000 Time (second!
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| Figure 7: Transient 4, Turbine Roll and Increased to Rated Power I
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| I 1--Temp (°F) - - Pressure (psig) I 800 1200 1160 1120 1080 700 I
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| 1040 1000 860 600 920 880 840 I
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| -600 500 760
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| *-680
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| .640 400 i 600 300 Stress.exe program calculates steady state values at beginning of transients. The time length for this 560. P 520 480 440 400 5-I transient can therefore be any value greater than 360 200 100 zero. The chosen length of 10 seconds has no" significance as there is no temperature change during this transient.
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| 320 280 240 200 160 I
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| 120 0-u 1000 2000 '3000 4000 5000 6000 7000 8000 80 40 0 I Time (seconds)
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| Figure 8: Transient 5, Daily Reduction 75% Power I I
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| File No.: VY-16Q-302 Revision: 0 Page 28 of 34 I F0306-OI RO I
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| V StructuralIntegrityAssociates, Inc.
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| !-Temp(F)-n - Pressure (psig)I 6MP 1080 1040 1000 960 920 5M0 880 840 800
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| -760 400 -720 F 680
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| -640
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| -600
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| .300 -560 520 E -480
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| -440 0C
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| - 400 200 -360
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| - 320
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| - 280
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| - 240 200 100 160
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| . 120 80
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| -40 0-5oo 1000 1500 2000 2500 3000 3500 4000 4500 5000 5500 6000 6500 Time (seconds)
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| Figure 9: Transient 6, Weekly Reduction 50% Power I -- Temp (F) - -- Pressure (psig) 450 0.
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| o S
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| 8 4,.
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| 4000 5000 Time (seconds)
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| Figure 10: Transient 9, Turbine Trip at 25% Power File No.: VY-16Q-302 Page 29 of 34 Revision: 0 F0306-01 RO
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| Structural Integrity Associates, Inc..
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| -Temp (T) -=Pressure (psig) 5oo 450 400 350
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| -300 250 E
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| 13-1- 200 150 100 so 40 0- 0 0 1000 2000 3000 4000 5000 600h0 7000 Time (seconds)
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| Figure 11: Transient 10, Feedwater Bypass
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| {- Temp (F) - -- Pressure (psig) 600 .1200 550 500 1000 450 400
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| ý'- 350 a 600 *=
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| 300 E' 250 a.
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| 200 150 100 50 0
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| 5000 10000 15000 . 20000 25000 Time (seconds)
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| Figure 12: Transient 11, Loss of Feedwater Pumps File No.: VY-16Q-302 Page 30 of 34 Revision: 0 F0306-OI RO
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| Inc.
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| VStructural Integrity Associates,
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| -Temp (F) -- Pressureps) 1080 1020
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| - 980
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| - 940 900 860
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| , 250 820 780 200 740 o 700 660 620 580 540 500
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| -30 970 1970 2970 3970 4970 Time (seconds).
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| .Figure 13: Transient*12, Turbine Generator Trip
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| -I Temp (°F) - -- Pressure (psig)fl 1100 1050 1000 950 350 300 250 E 200 0a 150 350 300 100 250 200 150 50 100 50 0
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| 1000 2000 3000 4000 5000 Time (seconds)
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| Figure 14: Transient 14, SRV Blowdown File No.: VY-16Q-302 Page 31 of 34 Revision: 0 F0306-O1 RO
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| StructuralIntegrityAssociates, Inc.
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| I- Temp (F) - -Pressure (psig) 4 L 1080 F1040 1000 960 400- 920 880 840
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| -800
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| -760 350 -720
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| - 680
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| -640
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| -600 7 4 300 -560.
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| -520 =
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| E .480
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| - 440 a
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| .400 250 .360
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| *320
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| . 280 240 200 200 160 120 s0 40 150 0 0 500 1000 1500 2000 2500 3000 3500 4000 4500 5000 5500 6000 6500 Time (seconds)
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| Figure 15: Transient 19, Reduction to 0% Power I- Temp (-F) - -Pressure (psig)]
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| 600 1100 1000 6
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| E 0.
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| 1!
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| 100 200 300 400 500 600 700 800 900 1000 Time (seconds)
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| Figure 16: Transient 20, Hot Standby (Heatup Portion)
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| File No.: VY-16Q-302 Page 32 of 34 Revision: 0 F0306-OIRO
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| V StructuralIntegrityAssociates, Inc.
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| I-Temp (*F) -- rsue(s 600 1100
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| (_'F) *
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| [*Temp -- Pressure (psig) [
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| 500 1000 900 This transient continues at steady state to 5451 seconds.
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| 800 5 E 0-200- 700 100 600 0- 1500 0 100 200 300 400 500 600 700 800 900 1000 Time (seconds)
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| Figure 17: Transient 20A, Hot Standby (Feedwater Injection Portion)
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| "The pressure between tis -* Temp (°F) - - Pressure (psig) point and the next is shown 600 as a straight line for - 1150 simplicity. The pressure 1100 actually followssaturation. 1050 1000 500" 950 9000
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| -850 500 400 750 700 650 'a
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| . 600 a 300 550 500 S .450 I-400 200 \ 350 300 250 200 100 150 100 1 50 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 Time (seconds)
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| Figure 18: Transient 21-23, Shutdown File No.: VY-16Q-302 Page 33 of 34 Revision: 0 F0306-01 RO
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| V StructuralIntegrityAssociates, Inc. "
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| -*Temp(OF) -*Pressure (psig) I 150 130 //\
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| /\
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| /\ 1600 1500 1400 I
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| /
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| I, 1300 110
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| / 1200
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| /
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| 1100
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| / 1000 70
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| /
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| /
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| I
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| /
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| 900 800 S I
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| E 700
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| /
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| 12 50-f 600 500 I
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| / -400 30
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| /
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| 10
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| /
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| /
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| * 300 200 I
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| -100
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| -104 0 100 200 300 400 500 600 700 Time (seconds) 800 900 1000 1100 1200
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| -,-~
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| 1300 0
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| I Figure .19:. Transient 24, Hydrostatic Test
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| -*Temp (*F)l -- Pressure (psig)
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| I 150 -
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| 130-
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| - 500 I
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| 110
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| . 400 I
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| 90 a70 so
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| . 300 I
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| I 200 a.
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| s.
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| 50 30 10 100 I
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| -101 0 1000 2000 3000 Time (seconds) 4000 5000 64)00 0
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| I Figure 20: Transient 25, Unbolt I File No.: VY-16Q-302 Revision: 0 Page 34 of 34 I
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| V IStructuralIntegrity Associates, Inc.
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| APPENDIX A
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| | |
| ==SUMMARY==
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| OF OUTPUT FILES File No.: VY-16Q-302 Page Al of Al Revision: 0 F0306-O1RO
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| V StructuralIntegrityAssociates, Inc. -
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| I Transient Table.xls BRresults.xls Definition of Transients Blend Radius Stress Summary In Computer files In Computer files I SEresults.xls Safe End Stress Summary In Computer files TRANSNT XX.INP Green.dat Input File for Each Transient Input File for Green Functions In Computer files In Computer files I
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| P-V XX.OUT Output File for Stress Analysis In Computer files GREEN.CFG FATIGUE.CFG Input File for Defining Green Function Input File for Defining Fatigue Analysis In Computer files In Computer files I
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| FATIGUE.DAT Input File for Fatigue Curves In Computer files FATIGUE.inp Input file for Fatigue Analysis from BRresults.xls or SEresults.xls In Computer files I FATIGUE.OUT Fatigue Output File In Computer files Where XX is defined for each transient.
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| I I
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| I I
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| I I
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| I File No.: VY-16Q-302 Page A2 of A2 Revision: 0 F0306-01 RO
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| REDACTED COPY 7ýý StructuralIntegrity Associates, Inc. File No.: VY-16Q-303 NEC-JH_06
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| ,CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME:
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| Environmental Fatigue Analysis of VYNPS CONTRACT NO.:
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| 10150394 CLIENT: PLANT:
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| Entergy Nuclear Operations, Inc. Vermont Yankee CALCULATION TITLE:
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| Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell/Bottom Head Document Affected Project Manager Preparer(s) &
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| Revision Pafes Revision Description Approval Checker(s)
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| 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-W. 1V,",
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| BI - B2 In computer files TelTy J. Herrmann 07/05/07 Page 1 of 24 C.011PIR-i's. "Vetrelm" F0306-0 IRO NEC065998
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| StructuralIntegrity Associates, Inc.
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| Table of Contents
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| ==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 CA LC U L A T ION S ........................................................ ................ ................................................. 6 4.1 RPV Lower Head ................................................................................ .............. .......... 7 4.2 R R Inlet N ozzle .......................................................................................................... 9 5.0 RE SU LT S O F A N A L Y SIS ........................................................................................................... 11u
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| ==6.0 CONCLUSION==
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| S AND DISCUSSION ................................................................................... 11 7 .0 REF E RE N C ES .............................................................................................................................. 12 APPENDIX A VY WATER CHEMISTRY INFORMATION [8] ............................................. Al APPENDIX B VY LICENSE DATE [10] ......... ................................ B I
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| 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
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| File No.: VY-16Q-303 Page 2 of 24 Revision: 0 F0306-OIRO NEC065999
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| StructuralIntegrity Associates, Inc.
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| | |
| ==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.
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| 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.
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| 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.
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| 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.
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| File No.: VY-16Q-303 Page 3 of 24 Revision: 0 F0306-01 RO NEC066000
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| V StructuralIntegrity Associates, Inc.
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| I 3.0 ASSUMPTIONS / DESIGN INPUTS I
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| 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:
| |
| For Carbon Steel [4, p. 691: Fe, = exp (0.585 - 0.00124T' - 0.10IS*T*O* C*) I 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:
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| Fen = exp (0.585 - 0.00124(25°C) - 0.101 S* T* 0* E*)
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| U
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| = exp (0.554 - 0.101 S* T* 0* F*)
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| I For Low Alloy Steel [4, p. 69]: Fn = exp (0.929 - 0.00124T' - 0.10lS*T*O* E*) I 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:
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| I Fn = exp (0.929 - 0.00124(25°C) - 0.101 S* T* 0* *)
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| =exp (0.898 - 0.101 S* T* 0*t')
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| I where [4, pp. 60 and 65]: Fen S :1:
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| = fatigue life correction factor S for 0 < sulfurcontent, S < 0.015 wt. %
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| I 0.015 for S > 0.015 wt. %
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| 0 for T < 150'C (T - 150) for 150*< T*< 350'C I T fluid service temperature ( 0C) 0* 0 for dissolved oxygen, DO < 0.05 parts per million (ppm) ln(DO/0.04) for 0.05 ppm < DO < 0.5 ppm I
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| = ln(1.2.5) for DO >0.5 ppm 0 for strain rate, e > 1%/see I 1n(s*) for 0.001 < e 1I%/sec
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| = ln(0.001) for 6 < 0.001%/sec I I
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| I File No.: VY-16Q-303 Page 4 of 24 Revision: 0 C~OP fAhr \'zridd~ P~&p~ iUa~y Jnf~rmqtirp I NEC066001 F0306-01RO I
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| StructuralInte/rity Associates, Inc.
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| For Tyqpes 304 and 316 Stainless Steel [5. p. 31]: F,,, =exp (0.935 - T* **O*)
| |
| wheret[5, pp. 25 and 31]: Fe, = fatigue life correction factor T* = 0 for T < 200'C
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| = 1 for T> 200 0 C T = fluid service temperature (°C)
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| F,* = 0 for strain rate, z > 0.4%/sec
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| = ln(E/0.4) for 0.0004 _<F _<0.4%/sec
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| = ln(0.0004/0.4) for F < 0.0004%/sec 0* = 0.260 for dissolved oxygen, DO < 0.05 parts per million (ppm)
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| = 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.
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| Therefore, based on Table I and for the purposes of this calculation, the following is assumed:
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| * 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.
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| * Recirculation line DO is 122 ppb pre-HWC and 48 ppb post-HWC.
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| * Feedwater line DO is 40 ppb for pre-HWC and 40 ppb for post-HWC conditions.
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| * RPV Upper Region DO is 114 ppb pre-HWC and 97 ppb post-HWC.
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| * RPV Beltline DO is 123 ppb pre-HWC and 46 ppb post-HWC.
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| * RPV Bottom Head Region DO is 128 ppb pre-HWC and 69 ppb post-HWC.
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| File No.: VY-16Q-303 Page 5 of 24 Revision: 0 e k 'tLah15 VU1d PP UjJ jtLLL y filkr l lttJfiie F0306-OIRO NEC066002
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| StructuralIntegrity 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 relevant EAF and EPU effects.
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| I I
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| 4.0 CALCULATIONS The analyses for the NUREG/CR-6260 locations identified in Section 2.0 are provided in this section. As previously noted, the fatigue calculations for 60 years for all locations make use of the U
| |
| 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., Efati*cJ*,ClErvcIEanalsv) 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 calculationare not the latest revision;forexample, Reference [12] (VYC-378, Revision 0) has been revised. However, the details necessary to peiform the evaluationsin this calculation are not necessarily contained in the latest revision of all documents. Therefore, wherever necessary, the appropriaterevision of the governing document is referenced in order to obtain all I
| |
| appropriateinputs 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 calculationsmay yield results slightly different than the values shown in the tables of this calculation due to round-off based on the significantfigures utilized by the spreadsheet usedfor these calculations.
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| I File No.: VY-16Q-303 Page 6 of 24 R e v i s io n : 0 . . e. n r VIrie ru p i i PT ct u y F0306-01 RO NEC066003
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| StructuralIntegrity Associates, Inc.
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| 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.
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| The fatigue calculation for 60 years for the RPV shell/bottom head location is also shown in Table 7.
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| 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).
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| Pile No.: VY-16Q-303 Page 7 of 24 Revision: 0 F0306-OIRO NEC066004
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| I C StructuralIntegrityAssociates, Inc. I 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 I
| |
| 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.
| |
| I 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]. I 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 I
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| CUF of 0.7364 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0).
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| I I
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| I File No.: VY-16Q-303 Page 8 of 24 Revision: 0 Lcntain~ '.'ZflJC~t~1 U~JJ ~ ic~tc~1 1~ at1on F0306-01 RO I
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| NEC066005 I
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| StructuralIntegrity Associates, Inc.
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| 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.
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| 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.
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| The fatigue calculation for 60 years for the RR inlet nozzle forging location is also shown in Table 9.
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| 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.
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| File No.: VY-16Q-303 Page 9 of 24 Revision: 0
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| .............d.r P oprietFi y I306- tmt F0306-0 t R0 NEC066006
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| I Structural Integrity Associates, Inc. I 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.
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| I The CUF for 40 years (without EAF effects) is 0.00 17.
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| The fatigue calculation for 60 years for the RR inlet nozzle safe end location is also shown in I
| |
| 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].
| |
| I 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 I CUF of 0.0199 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0)
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| I File No.: VY-16Q-303 Page 10 of 24 Revision: 0 C~mt~lii-i:5 "~hUor Pfopriztary infcrrnat.oa I NEC066007 F0306-0 IRO I
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| StructuralIntegrity Associates, Inc.
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| 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:
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| o Nozzle forging (low alloy steel) o Safe end (stainless steel)
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| * RPV shell/bottom head, consisting of the following bounding locations:
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| o Limiting bottom head shell inside surface location (low alloy steel) o Limiting RPV shell/shroud support location (low alloy steel)
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| 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.
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| 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.
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| File No.: VY-16Q-303 Page 11 of 24 Revision: 0 Containc 'Jenclc~ ifi oprictary 1t1f0 1 F0306-01RO NEC066008
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| StructuralIntegrity Associates, Inc.
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| | |
| ==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.
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| REDACTEDI
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| _ I File No.: VY-16Q-303 Revision: 0 "C0'h2ihL Vepndor prepi i*.tary Jnfnrm athon_
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| Page 12 of 24 3
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| F0306-0 RO NEC066009
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| V StructuralIntegrityAssociates, Inc.
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| : 14. GE Nuclear Energy Certified Design Specification No. 26A6019, Revision 1, "Reactor Vessel -
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| 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.
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| : 18. GE Nuclear Energy Certified Stress Report No. 23A4292, Revision 4, "Reactor Vessel -
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| 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.
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| File No.: VY-16Q-303 Page 13 of 24 Revision: 0 L.satain~.'Vc~~du~ lt upi iut~ti y iiiiG~ mat~cn F0306-01 RO NEC066010
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| V Structural IntegrityAssociates, Inc.
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| I Table 1: Water Chemistry Calculations I
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| Date of HWC Implementation: 11/01/2003 I
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| (seeAppendixA)
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| Availability of HWC System Since HWC Implementation: 98.54% (see Appendix A)
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| Projected Future HWC System Availability: 98.5% (see Appendix A, assume same as recent experience)
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| Recirculation Line DO pre-HWC: 122 ppb (see Appendix A)
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| I post-HWC: 48 ppb (see Appendix A)
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| Feedwater Line DO pre-HWC: 40 ppb (see Appendix A)
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| I post-HWC: 40 ppb (see Appendix A)
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| RPV Upper Region DO I
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| pre-HWC: 114 ppb (see Appendix A) post-HWC: 97 ppb (see Appendix A)
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| I RPV Beltline Region DO pre-HWC:
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| post-HWC:
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| 123 46 ppb (see Appendix A) ppb (see Appendix A) I RPV Bottom Head Reqion DO pre-HWC:
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| post-HWC:
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| 128 69 ppb (see Appendix A) ppb (see Appendix A)
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| I Plant Startup Date:
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| Time at pre-HWC Conditions:
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| Date of Calculations:
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| 03/~ ?2/1972 31.61 04/r 30/2007 (see Appendix B) years (calculated,includes leap years.) I Time Since HWC Implementation:
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| Projected Future Time for HWC Operation:
| |
| 3.49 24.90 years (calculated,includes leap years.)
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| years (calculated,includes leap years.) I Overall HWC Availability: 47%
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| 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 I
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| from the "Post-NMCA + HWC (OLP)", "Post-NMCA + HWC (EPU)", and "Future Operation" columns in Appendix A.
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| U I
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| I File No.: VY-16Q-303 Page 14 of 24 Revision: 0
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| - .... ;-, " --,NEC, Propri.tary ... o.. a.. o.
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| F0306-01 RO NEC066O1 1
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| V StructuralIntegrityAssociates, Inc.
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| 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)
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| Assume t,* = ln(0.001) = -6.908 (minimum)
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| For a BWR with HWC environment (post-HWC implementation): For a BWR with NWC environment (pre-HWC implementation)
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| DO = 48 ppb - 0.048 ppm DO = 122 ppb = 0.122 ppm, so 0* = ln(0.122,10.04) = 1.115 DO < 0.050 ppm, so 0* = 0 Thus: Thus:
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| T (°C) T (°F) F_. T (°C) T (°F) F,,
| |
| 0 32 2.45 0 32 2.45 50 122 2.45 50 122 2.45 100 212 245 100 212 2.45 150 302 2.45 150 302 2.45 200 392 2.45 200 392 4.40 250 482 2.45 250 482 7.89 288 550 2.45 288 550 12.29 Thus, maximum F_, 2.45 [T*=IT-150) to, T, 150'C] Thus, maximum Fn 12.29 Carbon Steel: Fe = exp(O.554 - 0.101S0T'Ogc*)
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| AssumeS* = 0.015 (maximum)
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| Assume = lIn(0.001) = -6.908 (minimum)
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| For a BWR with NWC environment (pre-HWC implementation)
| |
| For a BWR with HWC environment (post-HWC implementation):
| |
| DO = 48 ppb , 0.048 ppm DO = 122 ppb = 0.122 ppm, so 0' = ln(0. 122/0.04) - 1115 DO < 0.050 ppm, so 0' = 0 Thus: Thus:
| |
| T (°C) T (Ff) F_, T (°C) T (-F) Fe_
| |
| 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 3.12 250 482 1.74 250 482 5.59 288 550 1.74 288 550 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)
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| 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 Page 15 of 24 Revision: 0 Contain7; VodrPo-itr'Ifrnt-c F0306-0 IRO NEC066012
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| Structural IntegrityAssociates, Inc.
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| I Table 3: Bounding Fen Multipliers for Feedwater Line I
| |
| Low Alloy Steel: Fe = exp)0.898 - 0.101S'T'O7,)
| |
| Assume S" = 0.015 (maximum)
| |
| Assume :. = tn(O.001) = -6.908 (minimum)
| |
| I For a BWR with NWC environment (pre-HWC implementation):
| |
| I For a BWR with HWC environment (post-HWC implementation):
| |
| DO = 40 ppb = 0.040 ppm < 0.050 ppm so O* = 0 DO 40 ppb = 0.040 ppm < 0.050 ppm so 0* = 0 Thus: Thus:
| |
| T (°C) T (-F) Fen T (°C) T ('F) F_
| |
| 0 50 100 150 32 122 212 302 2.45 2.45 2.45 2.45 0
| |
| 50 100 150 32 122 212 302 245 2.45 2.45 2.45 I
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| 200 392 2.45 200 392 2.45 250 288 482 550 2.45 2.45 250 288 482 550 2.45 2.45 I Thus, maximum Fen = 2.45 [T*=(T-150) for Ta 1s0C) Thus, maximum F.,, 2.45 Carbon Steel: I_= esp(0.554 -0.10tS'T'OV;)
| |
| Assume S' = 0.015 (maximum)
| |
| I Assume r;. = ln(0.001) = -6.908 (minimum)
| |
| For a BWR with HWC environment (post-HWC implementation):
| |
| DO = 40 ppb = 0.040 ppm < 0.050 ppm so O0 = 0 Thus:
| |
| For a BWR with NWC environment (pre-HWC implementation):
| |
| DO = 40 ppb = 0.040 ppm < 0.050 ppm so 0 = 0 Thus:
| |
| I T (°C) 0 50 0
| |
| T ( F) 32 122 F_,
| |
| 1.74 1.74 T (-C) 0 5o T )°F) 32 122 Fee 1.74 1.74 I
| |
| 100 212 1.74 100 212 1.74 150 200 250 288 302 392 482 550 1.74 1.74 1.74 1.74 150 200 250 288 302 392 482 550 1.74 1.74 1.74 1.74 I
| |
| Thus, maximum Fe = 1,74 [T'= (T-150) for T t150°C] Thus, maximum F-, 1.74 There is no stainless steel in the Class t feedwater line.
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| I File No.: VY-16Q-303 Page 16 of 24 Revision: 0 (Jontacos V on ci or Vropriotary intormator F0306-01 RO I
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| NEC066013 I
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| StructuralIntegrity Associates, Inc.
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| 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): For a BWR with NWC environment (pre-HWC implementation):
| |
| D0 = 97 ppb = 0.097 ppm, so O0 = ln(0.097/0.04) = 0.886 DO = 114 ppb = 0. 114 ppm, so O; = Inf0.114/0.041 = 1.047 Thus: Thus:
| |
| T (0C) T (°F) Fen 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 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): For a BWR with NWC environment (pre-HWC implementation):
| |
| DO = 97 ppb = 0.097 ppm, so 0* = ln(0.097/0.04)= 0.886 DO = 114 ppb = 0114 ppm, so 0* = ln(O 114/0.04) = 1.047 Thus: Thus:
| |
| T (oC) T ('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 2.77 200 392 3.01 250 482 4.40 250 482 5.21 288 550 6.25 288 550 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 Page 17 of 24 Revision: 0 C,,Ju aitnu-' r/tixduu P-1 u ic 5 futjtntý.o F0306-OIRO NEC066014
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| StructuralIntegrity Associates, Inc.
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| V I
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| Table 5: Bounding F,, Multipliers for RPV Beltline Region I
| |
| Low Alloy Steel: Fen,= exp(0.898 -0.101S'T`O*,)
| |
| Assume S" = 0.015 (maximum)
| |
| Assume t,- = In(0.001) = -6.908 (minimum)
| |
| I For a BWR with HWC environment (post-HWC implementation):
| |
| DO = 46 ppb = 0.046 ppm DO < 0.050 ppm, so 0* = 0 Thus:
| |
| 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:
| |
| I T (-C) 0 50 100 T (°F) 32 122 212 Fen 2.45 2.45 2.45 T (°C) 0 50 100 T (F) 32 122 212 Fn 2.45 2.45 2.45 I
| |
| 150 302 2.45 150 302 2.45 200 269.45 288 392 517.01 550 2.45 2.45 2.45 200 269.45 288 392 517.01 550 4.42 10.00 12.43 I
| |
| Carbon Steel; Carbon Steel.
| |
| Thus, maximum Fn, 2.45 [T*=(T-150) for T, 150oq esp(0.554 -0.101STOu)
| |
| Fen= exp(0.554 - 0.101 S'T*O*e*)
| |
| Thus, maximum Fn = 12.43 I
| |
| Assume S* = 0,015 (maximum)
| |
| For a BWR with HWC environment (post-HWC implementation):
| |
| DO = 46 ppb = 0.046 ppm Assume F. = In(O.001) = -6.908 (minimum)
| |
| For a BWR with NWC environment (pre-HWC implementation):
| |
| DO = 123 ppb = 0.123 ppm, so 0* = In(0.123/0.04) = 1123 I
| |
| DO < 0.050 ppm, so O0 = 0 Thus:
| |
| T (°C) T (-F) Fen Thus:
| |
| T (-C) T (°F) Fen I
| |
| 0 32 1.74 0 32 1.74 50 100 150 200 122 212 302 392 1.74 1.74 1.74 1.74 50 100 150 200 122 212 302 392 1.74 1.74 1.74 3.13 I
| |
| 250 482 1.74 250 482 5.64 288 550 Thus, maximum Fen -
| |
| 1.74 1.74 fT'= (T- 150) fc, T , 150-Cl 288 550 Thus, maximum Fn 8.81 8.81 I
| |
| I 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°C Conservatively use T* = 1 for T > 2000C
| |
| * = 0 for , > 0.4%/sec Thus:
| |
| = ln(ý/0.4) for 0.0004 <= v <= 0.4%/sec so F0n =
| |
| so Fen ranges from 2.55 2.55 Thus:
| |
| so Fn=
| |
| so Fen ranges from 2.55 2.55 I
| |
| to 15.35 to 8.36
| |
| = ln(0.0004/0.4) foret- < 0.0004%/sec so Fen =
| |
| Thus, maximum Fen =
| |
| 15.35 15.35 so Fn =
| |
| Thus, maximum Fen 8.38 8.36 I
| |
| I File No.: VY-16Q-303 Page 18 of 24 I
| |
| Revision: 0 F0306-OIRO NEC066015
| |
| | |
| , StructuralIntegrity 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 HWC environment (post-HWC implementation): For a BWR with NWC environment (pre-HWC implementation):
| |
| DO = 69 ppb = 0.069 ppm, so 0' = In(0.069/0.04) = 0.545 DO = 128 ppb = 0.128 ppm, so 0* = In(0.128/0.04) = 1.163 Thus: Thus 0
| |
| T (0C) T )°F) Fen T (-C) T ( F) Fen 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 3.27 200 392 4.51 250 482 4.34 250 482 8.29 288 550 5.39 288 550 13.17 Thus, maximum Fen 5.39 [T'= (T-150) for T, 15O0C] Thus, maximum Fen 13.17
| |
| = exp(0.554 -0.101ST0'0 ')
| |
| Carbon Steel:
| |
| 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): For a BWR with NWC environment (pre-HWC implementation):
| |
| DO = 69 ppb = 0.069 ppm, so O" = In(0.069/0.04) = 0.545 DO = 128 ppb = 0.128 ppm. so 0* = In(0.128/0.04) = 1163 Thus: Thus:
| |
| T (-C) T (-F) Fen T (-C) T (-F) F00 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 2.31 200 392 3.20 250 482 3.08 250 482 5.88 288 550 3.82 288 550 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' ý 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 Page 19 of 24 Revision: 0 C= E)14 -A4rita qnpndo P1 t F0306-01R0 NEC066016
| |
| | |
| V StructuralIntegrity Associates, Inc.
| |
| I Table 7: EAF Evaluation for RPV Shell/Bottom Head Location I Component: RPV Shell/Bottom Head NUREG/CR-6260 CUF: 0.032
| |
| | |
| ==Reference:==
| |
| NUREG/CR-6260, p. 5-102 (for reference only) I Stress Report CUF: 0.0057 (for Point 14, see below)
| |
| Material: Low Alloy Steel (Material=A-533Gr. B per References [14] and [19])
| |
| Design Basis CUF Calculation for 40 years:
| |
| I Elatigue cure/Eanalysis = 1.149 Conservatively used minimum E of 26.1 from Section S2 Appendix of RPV Stress Report.
| |
| Power Uprate =
| |
| K, =
| |
| m =
| |
| 1.0067 1.000 2.0
| |
| =(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]
| |
| U n= 0.2 NB-3228.5 of ASME Code, Section III [I1]
| |
| SL+Pe+Q (see Note 1) 1.00 S,,=
| |
| K. (see Note 2) 26,700 25,762 psi (ASME Code, Section II, Part D [111)
| |
| Salt (see Note3) n (see Note 4) 200 N (see Note 5) 35,300 U
| |
| 0.0057 I
| |
| 44,b26 Notes 1. Pt +PR +o is obtainedfor Point 14 from p. A52 of VYC-378, Rev. 0.
| |
| : 2. K, computed in accordancemith NB-3228.5 of ASME Code, Section III.
| |
| 1 Total, U 4 0 = 0.0057 I
| |
| I
| |
| : 3. S,, = 0.5 *K "K, E Eo-s* *"PowerUprate "IPL +P6 +Q).
| |
| : 4. n for 40 years is the number of Heatup-Cooldown cycles, perp. 38 of VYC-378. Rev. 0.
| |
| : 5. N obtainedfrom 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.
| |
| Revsed CUF Calculation for 60 Years:
| |
| K. (see Note 2) Salt (see Note3) n (see Note 6) N (see Note 4) U I
| |
| PL+Ps+Q (see Note 1) 44,526 1.00 25,762 300 35,300 Total, U60 =
| |
| 0.0085 0.0085 I
| |
| Envronmental CUF Calculation for 60 Years:
| |
| Maximum Fen.HWC Multiplier for HWC Conditions =
| |
| Maximum F,.aNWC Multiplier for NWC Conditions =
| |
| 5.39 13.17 (from Table 6)
| |
| (from Table 6)
| |
| I U.w60 = U 6 0 x Fe.rNWC x 0.53 + U6 0 x FenHWC X 0.47 = 0.0809 Overall Multiplier = Uenv. 6 0 /U6 0 = 9.51 I
| |
| I File No.: VY-16Q-303 Page 20 of 24 Revision: 0 WG~~~
| |
| 4t -Ii 8 itlr 1rp irtar y nomto I NEC066017 F0306-OIRO I
| |
| | |
| W StructuralIntegrity 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 (p. S3-99d of RFV Stress Report)
| |
| Hydrotest K,, = 62,976 psi (p S3-97 o/ RPV Stress Report)
| |
| Improper Startup r5- = 28,060 psi fp. S3-98 of RPV Stress Report)
| |
| Improper Startup a, = -1,025 psi (p. S3-98 of RPV Stress Report)
| |
| Improper Startup Skin Stress = 156,099 psi (p. S3-98 of RPV Stress Report)
| |
| Improper Startup K,,; + Skin Stress = 223,443 psi (p. S3-98 of RPV Stress Report)
| |
| Warmup - = -5.707 psi tp. S3-99a of RPV Stress Report)
| |
| Warmup n,= -102 psi (p. S3-99a of PPV Stress Report)
| |
| Warmup Ktq, = -13.696 psi (p. S3-99a of RPV Stress Report)
| |
| Eiattgug cuavteiEanaty s = 1.0417 30.0 128,8 per $3-99f of RPV Stress Report and ASME Code fatigue curve Power Uprate 1.0067 =(549 100)/(546- roo) per4.4.1.bof26A6019. Roe. 1[14]
| |
| m= 2.0 NB-3228.5ofASME Code. Section Ittt1tt n= 0.2 NB-3228. 5 of ASME Code. Section t III[tt S, = 26,700 psi (ASME Code, Section (I, Part DC Qrt)
| |
| 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, ÷P +Q ts compuaed for Point 9 based on thef ( n, - cJ,) '..,,
| |
| (a. - Ca,) ,,,2 ] stress intensity
| |
| : 2. K.. computed in accordancevdth 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 obtainedfrom Figure 1-9.1 of Appendix I of ASME Code. Section lIl
| |
| : 6. n for 60 years is the projectednumber of cycles as follows:
| |
| Improper Startup = t cycles Hydrotest = t cycles Isothermal at 70oF 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 5.39 (from Table 6)
| |
| Maximum Fe-NeWc Multiplier for NWC Conditions 13.17 (from Table 6)
| |
| Uen5 . 60 = U60 x Fen.rtWc X 0.53 r- U6 0 x Fen.HWc X 0.47 0.7364 Overall Multiplier = Uenv-6o/Uuo- 9.51 File No.: VY-16Q-303 Page 21 of 24 Revision: 0 F0306-0 IRO NEC066018
| |
| | |
| I U StructuralIntegrity Associates, Inc. I Table 9: EAF Evaluation for RR Inlet Nozzle Forging Location I
| |
| Component: Recirculation Inlet Nozzle Forging NUREG/CR-6260 CUF:
| |
| Stress Report CUP:
| |
| Material:
| |
| 0.310
| |
| | |
| ==Reference:==
| |
| NUREG/CR-6260. p. 5-105 0.0433 Low Alloy Steel (for reference only)
| |
| (updatedfor Point 12, see belowf (Material =A-508 Cl. 1tper p. I-58-4 of CBIN Stress Report Section S8)
| |
| I Design Basis CUF Calculation for 40 years:
| |
| Etaliguecure/Eanalysis Power Uprate =
| |
| 1.1278 1.0067
| |
| =30.O/26.6(perpI-SS-24 of CBIN Stress Report Section S8 and ASME Code fatigue curve)
| |
| -(549- 100) (546- 100) per 4.4.1.b ot26A6019, Rev. 1[141 I
| |
| K, = 1.660 stress concentrationfactor (pý A270 of VYC-378, Rev. 0 [12])
| |
| m =
| |
| n =
| |
| St,, =
| |
| 2.0 0.2 26,700 NB-3228.5ofASME Code. Section 1tt[l it NB-3228.5 ofASMECode, Section Ill/It[]
| |
| psi (ASME Code, Section t1 Part Oft[))
| |
| I I
| |
| 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, U4 , 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. S,,* = 05 K,' "E ... E,,,,,,, '.,Power Uprate f[(PI +Pe, +Q) K, + Skin Stress].
| |
| I
| |
| : 5. n for 40 years is the number of Heatup-Cooldovn cycles, per p. 828 of lYC-378, Rev. 0 I
| |
| : 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-Cooldowncycles.
| |
| Revised CUF Calculation for 60 Years:
| |
| PL+PO+Q (see Note 1) 43.110 Skin Stress (see Note 2) 15,145 Ke (see Note 3) 1.00 S., (see Note 4) n (see Note 7) 49,224 300 N (see Note 6) 4,614 I Total, U. =
| |
| U 0.0650 0.0650 I
| |
| Environmental CUF Calculation for 60 Years:
| |
| Maximum Fen-1.WC Multiplier for HWC Conditions = 2.45 (from Table 5)
| |
| I Maximum FeNwc Multiplier for NWC Conditions = 12.43 (from Table 5)
| |
| Uenv-6o = U6o x Fen.NWC X 0.53 + U60 x Fen.HWC X 0.47 =
| |
| Overall Multiplier = Ue--6doUeo =
| |
| 0.5034 7.74 I
| |
| I I
| |
| I I
| |
| I File No.: VY-16Q-303 Page 22 of 24 Revision: 0 Cc~ntair 0 : '~~~~tdur Pr opi ietto y Itt fuc oo~t~cn F0306-O1 RO I
| |
| NEC066019 I
| |
| | |
| V StructuralIntegrity Associates, Inc.
| |
| Table 10: EAF Evaluation for RR Inlet Nozzle Safe End Location Component: Recirculation Inlet Nozzle Sale End NUREG/CR-6260 CUF: 0.310 (for reference only)
| |
| | |
| ==Reference:==
| |
| NUREG/CR-6260, p. 5-105 Stress Report CUF: 0.0017 (updated for Location 6-I, see below)
| |
| Material: Stainless Steel (316L per p. 8 of 23A4292, Rev. 4)
| |
| Design Basis CUF Calculation for 40 years:
| |
| Etatigue 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])
| |
| 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 6) U 47,183 36,972 1.00 26,385 2,076 1,242,266 0.0017 I Total, U40 = 0.0017 Notes: I. P L'+P +Q is obtained for Surface I (after weld overlay) from p. 117of Reference [18].
| |
| : 2. P+Q+Fis obtained for Point 6-1 from p. 118of 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÷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 1-9.2of 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= It 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 = 15.35 (from Table 2)
| |
| Maximum Fen.NWC Multiplier for NWC Conditions = 8.36 (from Table 2)
| |
| Uenv.6o = U6 o x Fen.NWC X 0.53 + U6, x Fen.HWC X 0.47 = 0.0199 Overall Multiplier = Uenv.6o/U60 = 11.64 File No.: VY-16Q-303 Page 23 of 24 Revision: 0 Contains ~r~-j~= Ps o~r>Qtnry Informt~t~cn F0306-0 IRO NEC066020
| |
| | |
| I
| |
| ýý StructuralIntegrity Associates, Inc.
| |
| I Table 11: Summary of EAF Evaluation Results for VY I No. Component Material 40-Year 60-Year (2)
| |
| Overall 60-Year Environmental Environmental I
| |
| Design CUF CUF Multiplier CUF (2,3) 1 2
| |
| RPV Shell/Bottom Head RPV Shell at Shroud Support Low Alloy Low Alloy Steel Steel 0.0057 0.0549 0.0085 0.0774 9.51 9.51 0.0809 0.7364 I
| |
| 3 Recirculation Inlet Nozzle Safe End Stainless Steel 0,0017 0.0017 11.64 0.0199 4
| |
| Notes:
| |
| Recirculation Inlet Nozzle Forging Low Alloy Steel 0.0433 0.0650
| |
| : 1. Updated 40-year CUF calculation based on recent ASME Code methodology and design basis cycles.
| |
| 7.74 0.5034 I
| |
| : 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 U
| |
| I I
| |
| I i
| |
| I I
| |
| I File No.: VY-16Q-303 Revision: 0 Page 24 of 24 I
| |
| U-4aFrtfttlll YCTICIOr H;0prietfffy 1lntCTTrrZTtt@ý -R NEC066021 F0306-01 RO I
| |
| | |
| V Structural IntegrityAssociates, Inc.
| |
| APPENDIX A VY WATER CHEMISTRY INFORMATION [8]
| |
| File No.: VY-16Q-303 Page A I of A2 Revision: 0 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°%.; 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 Page A2 of A2 Revision: 0
| |
| ~Contain.~ Vcudui Fi upi letal y I~~f~ 1 F0306-01 RO NEC066023
| |
| | |
| v StructuralIntegrity Associates, Inc.
| |
| APPENDIX B VY LICENSE DATE [10]
| |
| File No.: VY-16Q-303 Page B I of B2 Revision: 0 Con)1tai Vcd I OPT~ru ii l y inf-i MaIVIdIU F0306-0IRO NEC066024
| |
| | |
| I U StructuralIntegrityAssociates, Inc. I Vermont Yarkee Nu::ear Power S.ut-on License RenewalA .*ppUca.i, I
| |
| Michael A. BaIduzzi Vice President -
| |
| Pilarim NLiclear Power Station Pilarim NuLclear Power Station 600 Rocky Hill Road Plymouth, Mass achusetts 02360 I
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| Fred R_ Dacimo Vice President -
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| Indian Point Energy Center Indian Point Energy Center BleakJley Av-enue & Broadway Buchaanon. New York 105I11 I
| |
| Cooper Nuclear Paoer Station Randall K. srdington Vice President -
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| Operations Support 1200 Prospect Road PC. Box 98 I
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| Brownsville, NebraskRa 68321 Christocher J. Soitwarz Vice Presidemi -
| |
| Entergy Nuclear COpera.ions, Inc 440 Hamilton Avenue I Operations Suppor White Plains, New 'Yorkl, 10601 Theodore A. S VIce President -
| |
| n.li'._n Fivzpatrid Nuclear Power Station Fitzpatrick Nuclear Power Station 268 LalUe RBo'd East Lycomina, New Yorlk 13093 I
| |
| Jay K. Thfayer
| |
| %,icePresideni-Vermont Yankee Nuclear Power Entergy Nucl-ai ",-;ermnos Yank;ee corporate ONfire I Station 185 Old Ferry Road Braitle'ro, V7 0-5302-05010 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 years- i The license ',,as issued under Section i 4l of t'he Atomic Snergy I
| |
| Act of 1954 as amended. License renewal would extend the facility operating license froim nIdnIgh i FMFarch: 2 ý 2iO1,lto dnh glt Mr*ch'2 _2.2 This applicason also applies: to renewal of Those NRC source nmaterals, srrc'al nuclear nnaterial, I
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| and by-roduct material licenses that are subsumed or combined wih the fanity oper;.ltng license.
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| 1.1.6 Alteration Schedule I
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| ENSO does iot propose to consruct or alter any production or utilization facility in connection with this renew,,'al application.
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| I I
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| i*,. Administri.rive ýrformaton F'ae 1-4 I Page B2 of B2 I
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| File No.: VY-16Q-303 Revision: 0 eMu IiI iItr vScii 3~ Proprictary ~ 1 natio~
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| F0306-01 RO I
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| NEC066025 I
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| StructuralIntegrityAssociates, Inc. File No.: VY-16Q-304 Project No.: VY-16Q NEC-JH_07 CALCULATION PACKAGE PROJECT NAME:
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| Environmental Fatigue: Analysis of VYNPS CONTRACT NO.:
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| 10150394 CLIENT: PLANT:
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| Entergy Nuclear Operations, Inc Vermont Yankee Nuclear Power Station CALCULATION TITLE:
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| Recirculation Outlet Nozzle Finite Element Model Affected Project Manager Preparer(s)
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| Document Revision Description Approval Checker(s)
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| Revision Pages Signatures & Date Signature & Date 0 1-6, Initial Issue Terry J. Herrmann Minghao Qin Appendix:
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| AIA07/12/2007 A1-A20 *** 7/12/2007 Jennifer E. Smith 7/12/2007 Page 1 of 6 F0306-0 IRO
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| StructuralIntegrityAssociates, Inc.
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| I I
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| Table of Contents I
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| 1.0 2.0 OBJECTIVE ................................ .........................................
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| GEOMETRY / MATERIAL PROPERTIES ....... .................................................................
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| ......... 3
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| .... 3 I
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| 3.0 PROGRAM INPUT ....... ............ ................................. 3
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| ==4.0 REFERENCES==
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| ........................................................ 4 I APPEN DIX A RON_VY.IN P ...................................................................................................... Al I
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| I List of Tables I Table 1: M aterial Properties @ 300'F .......................................................................................... 5 I
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| I List of Figures I
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| Figure 1: AN SYS Finite Elem ent Model .................................................... ......................................... 6 File No.: VY-16Q-304 Page 2 of 6 Revision: 0 F0306-01 RO
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| StructuralIntegrityAssociates, Inc.
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| 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.
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| 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
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| * shell, and cladding. The model used the vessel radius multiplied by a factor 2.0 due to the model being axisymmetric.
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| The 2-D axisymmetric FEM was constructed using the dimensions and information from References
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| [4 and 5] based on ANSYS [2] finite element software. Figure 1 shows the resulting finite element model.
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| I The materials of the various components of the model are listed below:
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| Safe End- SA182 F316 [4] (l6Cr-l2Ni-2Mo)
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| ,0 Piping - SA376 TP316 [7] (l6Cr-12Ni-2Mo)
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| * Nozzle Forging - sA508 Class 2 [5] (3/4Ni-1/2Mo-1/3Cr-V)
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| * Vessel - SA533 Grade B [6] (Mn-I/2M0-1.2Ni)
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| * Cladding SA240 Type 304 [1, Sheet 7] (18Cr-8Ni)
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| 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°F which will be applied to the FEM model for Green's Function development.
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| 3.0 PROGRAM INPUT
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| . The input file, RONVY.INP (included in Appendix A),. creates the finite element model for the recirculation outlet nozzle.
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| I I
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| I File No.: VY-16Q-304 Page 3.of 6 Revision: 0 F0306-01 RO
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| StructuralIntegrity Associates, Inc.
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| I I
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| ==4.0 REFERENCES==
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| : 1. GE. Stress Report No. 23A4316, Revision 0, "Reactor Vessel Recirculation Outlet Safe End," I SI File No. VY- 16Q-204.
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| 2.
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| 3.
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| ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004.
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| American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part I D, 1998 Edition, 2000 Addenda.
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| : 4. Vermont Yankee Drawing 5920-06623, Rev. 0, (Hitachi, Ltd. Drawing No IOR290-127),
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| "Recirc. Outlet Safe End," SI File No. VY-16Q-204. I
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| : 5. Vermont Yankee Drawing 5920-00238, Rev. 4, (Chicago Bridge & Iron Company, Contract 6.
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| No. 9-6201, Drawing No. 21), "36"x28" Nozzles Mk NIA/B," SI File No. VY-16Q-204.
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| Vermont Yankee Drawing 5920-05752, Rev. 3, "Vessel & Attachments Material I
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| Identifications," SI File No. VY-16Q-209.
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| : 7. SI File No. VY- 16Q- 103, "Vermont Yankee Comments on VY- 16Q-304." I I
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| I I
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| I I
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| I I
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| I I
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| I File No.: VY-16Q-304 Revision' 0 Page 4 of 6 I F0306-OIRO I
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| V Structuralintegrity Associates, Inc.
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| Table 1: Material Properties @ 300'F (1)
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| 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)
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| Modulus of Elasticity, e-6 psi -28.0 26.7 27.0 27.0 Coefficient of Thermal Teml,7. .7 7.3 9.8 9.8 Expansion, e-6, in/in/°F Thermal Conductivity, 23.4 23.4 9.8 9.3 Btu/hr-ft-°F Thermal Diffusivity, 0.401 0.401 0.160 0.150 ft2 /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.
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| : 2. Calculated as fk/(pd)]/12 3 .
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| File No.: VY-16Q-304 Page 5 of 6 Revision: 0 F0306-0I RO
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| V StructuralIntegrity Associates, Inc.
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| Figure 1: ANSYS Finite Element Model File No.: VY-16Q-304 Page 6 of 6 Revision: 0 F0306-01 RO
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| V StructuralIntegrityAssociates, Inc.
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| I APPENDIX A RONVY.inp File No.: VY-16Q-304 Page Al of A20 Revision: 0 F0306-01 RO
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| StructuralIntegrityAssociates, Inc. .
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| finish
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| /clear,start
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| /prep7
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| /title, Recirc Outlet Nozzle Finite Element Model
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| /com, PLANE 182, 2-D Solid et,l,PLANE182,,, I" !Axisymmetric
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| /com, **************
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| /com, Material Properties @T=300F
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| /com, ****************************
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| /COM, Material #1 (Safe-End and Piping) SA-182 F316 (16Cr-12Ni-2Mo) mplex, 1,27E÷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
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| /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.
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| mp,kxx,2,23.4/3600/12 mp,c,2,0.119.
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| mp,nuxy,2,0.3 mp,dens,2,0.283 i
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| /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 mp,nuxy,3,0.3 mp,dens,3,0.283
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| -
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| I
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| /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
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| *AFUN,DEG
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| /com, *** Geometric Parameters ***
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| *set,vira,(103+3/16) !Actual Vessel Inner Radius to base metal used for model
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| *set,vir,2.0*vira !2.0 time of Vessel Inner Radius to base metal used for model i
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| *settvw,5+5/8-3/16 !Vessel Wall Thickness
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| *set,ri 1,25.75/2
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| *setro 1,28.375/2
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| *set,LI,5 i
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| *setjro2,28.375/2 File No.: VY-16Q-304 Page A2 of A20 Revision: 0 F0306-OIRO I
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| I Structural Integrity :. Associates,*Inc.
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| I I *set,L2,4.25
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| **set,ro3,28.875/2
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| *set,ro4,48.75/2
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| *set,L3,1.5
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| *set,L4,5.25
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| *set,L5,7+l/16
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| *set,L6,12+13/16
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| *set,1L7,9+/--7/8
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| *setL8,9+3/8
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| *set,L9,3 1+15/16
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| *set,LIO L9- 2-13/16-tvw
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| *set,ra,7
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| *set,rb, 1
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| *set,rc,5.25
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| *set,rd,2.5
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| -*set,tv,3/16
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| *set,dipmA,vir-(tv*2.0)+L9+ 11 +L 1 Vessel Centerline to End of Safe End used for model
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| *set,L21,1
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| *set,L22,4.25
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| *set,ri2l,(25+ 15/16)/2
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| /com, Geometry local, 13,0,,dimA....
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| csys, 13
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| /com, Begin at end of Safe-End - Carbon Section k, 1, rio, -1l*(dimA) k, 2, ril +tv, -1 *(dimA) k, 3, ro 1, -1*(dimA) k, 41,r I*(dimA-L
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| - 1) k, 5, ri l+tv, - I*(dimA-L1L) k, 6, ro3,- l*(dimA-L1) k, 7, ri 1, - I-L2) T*(dimA-L 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*(dimAýL 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))
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| 1,19,22 File No.: VY-16Q-304 Page A3 of A20 Revision: 0 F0306-O1 RO
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| ! S.tructu~ral IntegrityAssociates, Inc.
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| LFILLT, 1,4,rb k, 25, ri 1,
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| , -1 *(dimA-L ýL2-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, LSTR, 6,
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| 9, 9
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| 12 i
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| LSTR, 12, 15
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| *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, LSTR, LSTR, 26, 25, 4,
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| 28 27 1
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| I LSTR, 1, 2 LSTR, 2, 3 LSTR, 3, 6 LSTR, 5, 2 LSTR, LSTR, LSTR, 7,
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| 8, 12, 8
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| 9 I1 I
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| 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
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| U StructuralIntegrity Associates, Inc.
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| 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,,
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| 1*
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| S LFILLT,43,8,rd,,
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| LFILLT,39,38,rc,,
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| 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)
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| 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 IRO
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| StructuralIntegrityAssociates, Inc.
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| 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
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| *FITEM,2,12I FITEM,2,17 AL,P51X FLST,2,4,4 FITEM,2,16
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| . FITEM,2,17 FITEM,2,31 FITEM,2,34 I
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| AL,P51X FLST;2,4,4 FITEM,2,36.
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| FITEM,2,13 FITEM,2,33 FITEM,2,18 AL,P51X U
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| FLST,2,4,4 FITEM,2,19 FITEM,2,18 FITEM,2,35 FITEM,2,34 AL,P51X FLST,2,4,4 I
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| FITEM,2,2 FITEM,2,5 FITEM,2,36 FITEM,2,21 ALP5 IX FLST,2,4,4 FITEM,2,20 i
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| 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
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| V StructuralIntegrityAssociates, Inc.
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| . 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
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| StructuralIntegrityAssociates, Inc.
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| 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*
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| CMSEL,S,_Yl AATT, 2,, i, .0, CMSEL,S,_Y .
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| 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
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| !/com, Map mesh areas FLST,5,10,4,ORDE,10 FITEM,5,51 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
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| StructuralIntegrityAssociates, Inc.
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| 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*
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| 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 I CM,_YI,L1NE CMSEL,,_Y LESIZE,_Y 1,,,20 ..... 1 1*
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| 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 1*
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| .,,,40 ..... I File No.: VY-16Q-304 Page A9 of A20 Revision: 0 F0306-01 RO
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| Structural Integrity Associates, Inc.
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| 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*
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| 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*
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| 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*
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| '*
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| 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
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| N StructuralIntegrity Associates, Inc.
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| !Modify the safe end ID FLST,2,6,5,ORDE,2
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| * 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, ,
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| FLST,3,2,3,ORDE,2 FITEM,3,3 FITEM,3,6 KGEN,2,P5 IX,, ,-ro2+ri21 .... 0.
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| FLST,3,1,3,ORDE, 1 FITEM,3,2 I KGEN,2,P51X, ... L22, ,0 FLST,3,3,3,ORDE,3 FITEM,3,1 FITEM,3,-2 I FITEM,3,4 KGEN,2,P5 lX, , ,tv, , -, ,O FLST,3,2,3,ORDE,2 I *FITEM,3, !0 FITEM,3,-1I KGEN,2,P51X,,, ,-(L3-L21 ),, ,0 FLST,3,1,3,ORDE, I FITEM,3,23 KGEN,2,P5 IX,, ,5,,, ,O LSTR, 23, 40 FLST,2,2,4,ORDE,2 FITEM,2,9 FITEM,2,12 LPTN,P5 IX LDELE, 16, ,1 FLST,2,4,3 FITEM,2,11 I FITEM,2,23 FITEM,2,41 FITEM,2,12 A,P51X I File No.: VY-16Q-304 Page All of A20 Revision: 0 F0306-0IRO
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| StructifralIntegrityAssociates, Inc..
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| 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.
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| 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 FLST,2,4,3 I
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| 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 FITEM,5,-20 I
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| *CM,_YAREA ASEL .... P51X CM,_YIAREA CMSEL,S,_Y I
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| .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
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| 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
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| LESIZE,_YI ,,15,, ,,!
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| FLST,5,4,4,ORDE,4 I FITEM,5,31 FITEM,5,48 FITEM,5,50 FITEM,5,52 CM,_YLINE LSEL .... P51X
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| ,CM,_YI,LINE I *
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| *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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| FITEý4,5,14 FITEM4,5,30 FITEM,5,32 CM_YLINE LSEL .... P5IX CM,_YI,LINE I CMSEL,,_Y 1* _
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| LESIZE,_Y 1,,.,6 ..... 1 I . FLST,5,3,4,ORDE,3 FITEM,5,11 FITEM,5,17 I FITEM,5,49 CMY,LINE LSEL .... P51X CM,_YI,LNE.
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| CMSEL,_Y LESIZE,_YI,,, 12....1 1*
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| FLST,5,3,4,ORDE,3 FITEM,5,27 FITEM,5,29 I
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| Structural IntegrityAssociates, Inc.
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| FITEM,5,51 CM,_Y,LINE LSEL .... P51X CM,_YI,LINE CMSEL,,_Y 1*
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| LESIZE,_YI,, ,25,,.. 1 FLST,5,8,5,ORDE,4 FITEM,5,1 FITEM,5,-6 FITEM,5,19 I
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| FITEM,5,-20 CM,_YAREA ASEL .... P51X CM,_YI,AREA CHKMSH,'AREA' CMSEL,S_-Y 1*I MSHKEY, .
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| AMESH,_YI MSHKEY,0 1*
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| CMDELE,_Y CMDELE,_Y2 CFLST,2,2,5,ORDE,2
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| * FITEM,2,17 FITEM,2,- 18 ACLEAR,P51X i csys,0.
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| * k, 51,62/2,0,0 k, 52,62/2,60,0 LSTR, 51, 52 I
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| "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 FITEM,2,-61 i
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| 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
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| 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 E CM,_YAREA ASEL....
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| CM,_YI,AREA 18 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 E CM,_YAREA ASEL ....P51X CM,_YI,AREA CMSEL,S,-Y 1*
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| I CMSEL,S,_Y I AATT, .3,, 1,. 0, I CMSEL,S,_Y CMDELE_-Y CMDELE_-Y1 1*
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| CM,_YAREA
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| * ASEL.... 21 CM,_YI,AREA CMSEL,S,_Y
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| *CMSEL,S,_Y1 AATT, 4,, 1, 0, CMSEL,S,_Y I File No.: VY-16Q-304 Page A15 of A20 Revision: 0 F0306-OIRO
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| 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
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| .CM,_YLINE U
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| 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 ASEL .... P5IX I
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| CM,_YIAREA CHKMSH,'AREA' M I CMSEL,S,_Y MSHKEY,1 AMESH,_YI MSHKEY,O
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| *CMDELE,_Y CMDELE,_Y I CMDELE,_Y2 FLST,5,2,5,ORDE,2 FITEM,5,21
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| *FITEM,5,-22 CM,_YAREA ASEL .... P51X CM,_YI ,AREA CHKMSH,'AREA' CMSEL,S,Y I MSHKEYJ,1 AMESH,_Y1 MSHKEY,O 1*
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| File No.: VY-16Q-304 Page A16 of A20 I Revision: 0 F0306-OlRO
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| * I VStructural IntegrityAssociates, Inc.
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| CMDELE,_Y CMDELE,.YI I CMDELE,_Y2 1*
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| !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 I KGEN,2,15 .... 1 1/16,, ,0 KGEN,2,44, ,, ,-0.25, ,0 KGEN,2,14 .... 11/16-1.375*tani(7.5),...0 KGEN,2,46,, , ,-0.25,, ,0 H i FLST,2,3,4,ORDE,3 FITEM,2,2 FITEM,2,20 I FITEM,2,-21 LDELE,P51X LSTR, 21, 44 LSTR, 44, 45 LSTR, 45, 15 LSTR, 17, 46 LSTR, 46, .47 LSTR, 47, 14 I LSTR, 46, 44 LSTR, 45, 47 LSTR, 13, 16 FLST,3,2,3.,ORDE,2 FITEM,3,46 FITEM,3,-47 I KGEN,2,P5 IX,, ,-0.25 .... 0 LSTR, 48, 46 LSTR, 49, 47
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| * FLST,2,3,4,ORDE,3 I : FITEM,2,61 FITEM,2,64 FITEM,2,-65 I LPTN,P51X FLST,2,2,4,ORDE,2 FITEM,2,70 FITEM,2,-71 LDELE,P5 1X,.
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| FLST,2,4,4 FITEM,2,67 I FITEM,2,39 FITEM,2,68 FITEM,2,3 AL,P51X File No.: VY-16Q-304 Page A17 of A20 Revision: 0 F0306-01 RO
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| 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
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| ,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!
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| 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
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| *ASEL.... 10 CM,_YI,AREA CMSEL,S,_Y 3 CMSEL,S,_Y1 AATT, 2,, 1, 0,
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| .CMSEL,S,_Y CMDELE,_Y I
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| 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*
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| CMSEL,S,_Yl
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| ' AATT, 3,, 1, 0, CMSEL,S, Y
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| *CMDELE,_Y File No.: VY-16Q-304 Page A18 of A20 i Revision: 0 F0306-0I RO I
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| V StrulcturalIntegrityAssociates, Inc.
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| I CMDELE_,2Yl FLST,5,2,5,ORDE,2.
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| 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
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| .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
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| .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*
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| MSHKEY, 1 AMESH,_Y1 MSHKEY,0 1*
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| CMDELE,_Y I File No.: VY-16Q-304 Page A19 of A20 Revision: 0 F0306-OIRO
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| CMDELE,_Y1 CMDELE,_Y2 I
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| I 1*
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| FLST,5,4,5,ORDE,2 FITEM,5,23 FITEM,5,-26 CM,_YAREA ASEL .... P51X CM,_YI,AREA I
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| CHKMSH,'AREA' CMSEL,S,_Y I MSHKEY, I AMESH,_YI MSHKEY,O 1*
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| I CMDELE,_Y CMDELE,_Y1 CMDELE,_Y2 I save finish I
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| I File No.: VY-16Q-304 Revision: 0 Page A20 of A20 I F0306-OI RO I
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| StructurallIntegrity Associates, Inc. File No.: VY-16Q-305 NEC-JH 08 CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME:
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| Environmental Fatigue Analysis of VYNPS CONTRACT NO.:
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| 10150394 CLIENT: PLANT:
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| Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE:
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| Recirculation Outlet Stress History Development for Nozzle Green Function Project Manager Preparer(s) &
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| Document Affected Revision Description Approval Checker(s)
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| 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
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| V Structural IntegrityAssociates, Inc. I Table of Contents I
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| I 1.0 OBJECTIVE.............................................................................................. 4 2.0 RECIRCULATION OUTLET NOZZLE MODEL ...................................................
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| 3.0 APPLIED LOADS.......................................................................................
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| 4 4
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| I 4.0 THERMAL AND PRESSURE LOAD RESULTS....................................................
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| ==5.0 REFERENCES==
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| ..........................................................................................
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| 7 10 I APPENDIX A FINITE ELEMENT ANALYSIS FILES ................................................ Al I
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| I List of Tables I Table 1: Material Propertie~s @ 300'F............. ................ 1 I
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| Table 2: Pressure Results....................................................................................1.I1 Table 3: 0% Flow Regions 1 and 3 Heat Transfer Coefficients.......................................... 12 I Table 4: 0% Flow Region 5 Heat Transfer Coefficient ................................................... 13 I
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| File No': VY-16Q-305 Revision: 0 Page 2 of 29 I
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| F0306-01I RO I
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| SStructural Integrity Associates, Inc.
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| 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
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| *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 Page 3 of 29 Revision: 0 F0306-O1 RO
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| StructuralIntegrityAssociates, Inc.
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| 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.
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| 2.0 RECIRCULATION OUTLET NOZZLE MODEL An axisymmetric finite element model of the recirculation outlet nozzle was developed in Reference
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| [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.
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| 3.0 APPLIED LOADS Both pressure and thermal loads will be applied to the' finite element model.
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| 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:
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| ~I Pa. P~ (Di2)2 where:
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| 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)
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| 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.
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| FileNo.: VY-16Q-305 Page 4 of 29 Revision: 0 F0306-OI RO
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| Structural Integrity Associates, Inc.
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| 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.
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| 3.2.1 Heat Transfer Coefficients; The heat transfer coefficients for the 100% flow and 50% flow cases were calculated from Reference
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| [4] as follows:
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| hDf =h 30 0 p)0826 )0.
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| 25_ 26 Where:
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| hDf= the heat transfer coefficient at a Diameter and flow rate h 300 = the heat transfer coefficient from Reference *[4] at 300'F fDf= the flow rate corresponding to hDf (fi/sec)
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| DDf = the diameter corresponding to hDf (in)
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| The heat transfer coefficients for 0% flow were calculated in spreadsheet Htcoeffs.xls for natural convection and are shown in Tables 3 and 4.
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| As shown in Figure 5, the following heat transfer coefficients were applied:
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| Region I The heat transfer coefficient, h, for 100% flow is 4789 1-3"6F 3577.8 BTU/hr"ft2 at 3000 F. [4]
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| where 17.364 ft/sec is converted from 28,294 GPM and 25.8 in ID.
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| The heat transfer coefficient, h, for 50% flow is 4789 8.-8) 2054.9 BTU/hr-ft 2-°F at 300°F. [4]
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| where 8.682 ft/sec is converted from 14,147 GPM and 25.8 in ID.
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| The heat transfer coefficient, h, for 0% flow is 112.34 BTU/hr-ft2 -°F at 300TF. [Table 3, for natural convection]
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| File No..: VY-16Q-305 Page 5 of 29 Revision: 0 F0306-OI RO
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| StructuralIntegrityAssociates, Inc. I I
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| Region 2 The heat transfer coefficient for Region 2 is linearly transitioned from the value of the heat I
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| transfer coefficient used in Region 1 to the value used for Region 3.
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| I Region 3 (the point between Region 2 and Region 4) 0.8 0.2 I
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| The heat transfer coefficient, h, for 100% flow is 4789 BTU/hr-ft2-°F at 300 0 F. [4]
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| 17.364) .*26 =3361 I
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| where the flow rate is the same as that for Region 1, and the ID is 35.49 in. I The heat transfer coefficient, h, for 50% flow is 4789 8.62 0-. 26 0.21930.9 BTU/hr-ft2 -°F at 300 0 F. [4]
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| 25 35.49 I
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| where the flow rate is the same as that for Region 1, and the ID is 35.49 in.
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| ,I The heat transfer coefficient, h, for 0% flow is 112.34 BTU/hr-ft2 -°F at 300TF. using the same HTC as Region 1 [Table 3, for natural convection]
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| I Region 4 I
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| 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 I
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| in Region 5.
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| I Region 5 I The heat transfer coefficient, h, for 100% flow is 0.5 x 3577.8 1788.9 BTU/hr-ft2'-F at 300°F. [4] I 1027.4 BTU/hr-ft2 -- F at The heat transfer coefficient, h, for 50% flow is 0.5 x 2054.9 300°F. [4] I The heat transfer coefficient, h, for 0% flow is 101 BTU/hr-ft2-°F at 300 0 F. [Table 4, for natural convection] by using 40 in. hydraulic diameter [4]. I File No.: VY-16Q-305 Page 6 of 29 I Revision: 0 F0306-O1RO I
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| 3 StructuralIntegrityAssociates, Inc.
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| SRegion_ 6 The heat transfer coefficient, h, is 0.4 BTU/hr-ft2 -OF [4].
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| 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:
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| Regions 1 to 5 T =500OF - 100 0 F Region 6 T= 120°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.
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| 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%,
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| and 0% flow rates, respectively.
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| * The critical safe end location was chosen as node 6395, which has the highest stress intensity due to.
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| 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
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| * seconds.
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| 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.
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| 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.
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| I File No.: VY-16Q-305 Page 7 of 29 Revision: 0 F0306-01 RO
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| VStructural Integrity Associates, Inc.
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| The stress time history for the critical paths was extracted during the stress run for 100% flow rate.
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| 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.
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| The stress time history for the critical paths was extracted during the stress run for 50% flow rate.
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| This produced two files, MFSE.OUT and MFBR.OUT which contains the thermal stress history..
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| 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.
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| The stress time history for the critical paths was extracted during the stress run for 0% flow rate.
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| 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.
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| 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, PSE.OUT and PBR.OUT for the safe end and blend radius locations, respectively.
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| I 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.l 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 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.
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| File No.: VY-16Q-305 Page8 of 29 Revision: 0 F0306-01 RO
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| 1 Structural IntegrityAssociates, Inc.
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| 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.
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| File No.: VY-16Q-305 Page 9 of 29 Revision: 0 F0306-O1 RO
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| | |
| ==5.0 REFERENCES==
| |
| | |
| I
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| : 1. SI Calculation No. VY-16Q-304, Revision 0, "Recirculation Outlet Nozzle Finite Element 2.
| |
| Model" ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004. I
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| : 3. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 4.
| |
| 1998 Edition, 2000 Addenda.
| |
| CB&I, RPV Stress Report Section: T9 "Thermal Analysis Recirculation Outlet Nozzle I Vermont Yankee Reactor Vessel." 9-620 1, S1 document, VY- 16Q-204.
| |
| 5.
| |
| 6.
| |
| J. P. Holman, "Heat Transfer," 4th Edition, McGraw-Hill, 1976.
| |
| J. P. Holman, "Heat Transfer," 5th Edition, 1981.
| |
| I
| |
| : 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.
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| I I
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| 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 Il3Cr-V) (!8Cr-8Ni) (lGCr-12NM -
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| 1/2Ni)
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| _________ 2Mo)
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| Modulus of Elasticity, e- 28.0 26.7 27.0 27.0 psi 28._2.7270_7.
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| 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/in3 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)
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| Safe End 11350 11490 Blend Radius 33640 31300 File No.: VY-16Q-305 Page 11 of 29 Revision: 0 F0306-01 RO
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| StructuralIntegrityAssociates, Inc.
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| I Table 3: 0% Flow Regions 1 and 3 Heat Transfer Coefficients I Pipe Inside Diameter, D = 2S H, inches = 2.150 ft Outer Pipe, Inside radius, r. = 12.9 inches =
| |
| = 0.655 1.075.
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| 0.328 m
| |
| ft m
| |
| I Inner Pipe Outside Diameter, D = na inches = 0.000 ft I
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| = 0.000 m 000 Inner Pipe, Outside radius, r = 0 inches 0.000 ft 0.000 m Fluid Velocity, V = 17.364 ft/sec = 8A?95 gpm= 12.3 Mib/hr Characteristic Length, L = D = 2.150 ft= 0.655 m (Outside Ttuid - Tsurfý., AT 8,40 4.67 12.00 6.67 24.00 13.33 36.00 20.00 48.00 26.67 60.00 33.33 72.00 40.00
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| °F C I Value at Fluid Temperature, T [3] Units
| |
| . .hm Water Property k
| |
| ncv Conversion Factor f1l 1.7307 70 21.11 0.5997 0.3465 100 37.78 0.6300 0.3640 200 93.33 0.6784 0.3920 300 148.89 0.6836 0.3950 400 204.44 0.6611 0.3820 500 260.00 0.6040 0-3490 600 315.56 0.5071 0.2930 W/m-°C
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| -F C
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| Btu/hr-ft-°F I
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| CP 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-°C (Sp.ficHeat) p (Density) 16.018 1.000 997.1 62.3 0.998 994.7 62.1 1.010 962.7 60.1 1.030 917.8 57.3 1.080 858.6 53.6 1.190 784.9 49.0 1.510 679.2 42.4 Btu/Ibm-°F kg/m Ibm/ft 3
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| 3 I
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| 3 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 /m -.c (Volumetric Rate of Expansion) 9 (Gravitational Constant) 0.3048 1.05E-04 9.806 32.17 1.80E-04 9.806 32.17.
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| 3.70E-04 9.806 32.17 5.60E-04 9.806 32.17 7.80E-04 9.806 32.17 1.10E-03
| |
| .9.806 32.17, 1.75E-03 9.806 32.17 3 3 ft /ft -°F mIS 2
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| 2
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| .tts I
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| .. 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 Pr (Prandtl Number)
| |
| Calculated Parameter
| |
| ...
| |
| Formula 6.69E-04 6.980 70 4.58E-04 4.510 100 2.06E-04 1.910 200 1.30E-04 1.220 300 9.30E-05 0.950 400 7.00E-05 0.859 500 5.79E-05 1.070 600 Ibm/ft-s
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| -
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| -F I
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| Reynold's Number, Re pVD/p 3473691 5061789 10891437 16454670 21515912 26132199 27337904 -
| |
| Grashof Number, Gr Grashof Number, Gr 6 Rayleigh Number, Ra 3
| |
| gPATL /(Wp)
| |
| .GrPr 3
| |
| 2 gpAT(r.-ri) /(p.P) 3 2441754517 1.2697E+10 2.417E+11 3.05E+08 1.59E+09 3.02E+10 17043446531 5.7265E+10 4.616E+11 1.252E+12 3.977E+12 1.034E+13 1.57E+11 4.97E+11 1.29E+12 1.528E+12 3.778E+.12 8.883E+12 2.31172E+13 2.16049E+13 2.70E+12
| |
| -
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| -
| |
| -
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| I 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°pr°- 1D 4
| |
| 7,823.02 9,326.34 13,148.12 15,405.24 16,705.40 17,126.15 16,275.32 W/m -°C 2
| |
| 2 I
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| 1,377.74 1,642.50 2,315.56 2,713.07 2,942.05 3,016.15 2,866.31 Btu/hr-ft -°F From [1]:
| |
| Inside Surface NaturalConvection Heat TransferCoefficient:
| |
| Case: Enclosed cylinder C= n 5 2
| |
| Hfe C(GrPr)nk/L 161.85 258.65 469.34 637.89 773.57 875.17 933.22 W/m -°C 2
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| 32.03 45.55 82.66 1123412 . 136.24 154.13 164.35 Btu/hr-ft -°F I
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| Table 4: 0% Flow Region 5 Heat Transfer. Coefficient Heat Transfer Coefficients
| |
| | |
| ==References:==
| |
| : 1. J. P. Holman, "HeatTransfer,- 4th Edition,McGraw-Hill, 1976.
| |
| : 2. J. P. Holman, "HeatTransfer,' 5th Edition, 1981.
| |
| : 3. N. P. Cheremisinoff, "HeatTransfer Pocket Handbook," Gulf Publishing Co., 1984.
| |
| (RequiredInputs are Shaded!)
| |
| Title =_ ". ,
| |
| Pipe Inside Diameter, D =4 dQOO inches = 3.333 ft
| |
| = 1.016 m Outer Pipe, Inside radius, r. = 20 inches = 1.667 ft 0.508 m Inner Pipe Outside Diameter, D = f, inches = 0.000 ft
| |
| = 0.000 m C).oC' I <
| |
| Inner Pipe, Outside radius, r = 0 inches 0.000 ft 0.000 m Fluid Velocity, V = 7.224 fllsec = -2g8293E pm= 12.3 Mlb/hr Characteristic Length, L = D = 3.333 ft= 1.016 m (Outside) Tluid - Tu,-ram, AT 8.40 12.00 24.00 36.00 4,8.00 60.00 72.00 -F
| |
| = 4.67 6.67 13.33 20.00 26.67 33.33 40.00 °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 3 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/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 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 ft3/ft3-oF 2
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| 9 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 m/s (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
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| ......
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| 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) '
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| 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 0.023Re0 ePro°k/D 3,552.89 4,235.64 5,971.33 6,996.42 7,586.90 7,777.99 7,391.58 W/m2 -°C 625.71 745.95 1,051.63. 1,232.17 1,336.16 1,369.81 1,301.76 Btu/hr-ft 2-°F From [1]:
| |
| Inside Surface NaturalConvection 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 -°C 28.70 40.82 74.07 g0.v8Y, 122.09 138.13 147.29 Btu/hr-ft2-°F File No.: VY-16Q-305 Page 13 of 29 Revision: 0 F0306-O1 RO
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| VStructuralIntegrityAssociates, Inc.
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| ELEMENTS APR 19 2007 13:03:51 Recirc Outlet Nozzle Finite Element Model Figure 1: ANSYS Finite Element Model File No.: VY-16Q-305 Page 14 of 29 Revision: 0 F0306-01 RO
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| C StructuralIntegrity Associates, Inc.
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| EL EMENT S ANN, APR 19 2007 13:29:35 CF PRES- NORMI
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| -5082
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| -3730
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| -30,541
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| -2379
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| -1703
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| -1027ý
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| -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 Page 15 of 29 Revision: 0 F0306-01 RO
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| 00 7 34 7
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| Figure 3: Recirculation Outlet Nozzle Pressure Cap Load File No.: VY-16Q-305 Page 16 of 29 Revision: 0 F0306-0 1RO
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| Figure 4: Recirculation Outlet Nozzle Vessel Boundary Conditions File No.: VY-16Q-305 Page 17 of 29 Revision: 0 F0306-01 RO
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| V StructuralIntegrity Associates, Inc.
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| AREAgS S MAT: NUM APR 19 2007 13:35:14 Region 5 Region 6 Region 4 Region 2 I Region 1 Region 3 x
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| Recirc Outlet Nozzle Finite Element Model, Figure 5: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries File No.: VY-16Q-305 Page 18 of 29 Revision: 0 F0306-01 RO
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| V StructuralIntegrityAssociates, Inc.
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| NODAL SOLUTION AN Y,.
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| APR 24 2007 STEP=322 09:05:10 SUB =1 TIME=5.1 SINT (AVG)
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| DMX =.810882 SMN =169.035 SMX =121100
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| ~iW~7' ~
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| 169.035 27043 53916 80790 107663 13606 40479 67353 94226 121100 Recirc Outlet Nozzle Finite Element Model Figure 6: Safe End Critical Thermal Stress Location File No.: VY-16Q-305 Page 19 of 29 Revision: 0 F0306-01RO
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| ELEMENTS AN7 APR 19 2007 MAT NUM 13:57:29 PATH Node 6395 Recirc Outlet Nozzle Finite Element Model Figure 7: Safe End Limiting Linearized Stress Paths File No.: VY-16Q-305 Page 20 of 29 Revision: 0 F0306-0 IRO
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| Figure 8: Blend Radius Limiting Pressure Stress Location File No.: VY-16Q-305 Page 21 of 29 Revision: 0 F0306-OI RO
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| Figure 9: Blend Radius Linearized Stress Path File No.: VY-16Q-305 Page 22 of 29 Revision: 0 F0306-O I RO
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| I Total Stress Intensity 03 Time (sec)
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| Figure 10: Safe End 100% Flow Total Stress Intensity Total Stress Intensity C,,.
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| Time (sec)
| |
| Figure 11: Blend Radius 100% Flow Total Stress Intensity File No.: VY-16Q-305 Page 23 of 29 Revision: 0 F0306-01 RO
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| VStructuralIntegrityAssociates, Inc.
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| 140000 (J2 200 400 600 800 1000 Time (sec)
| |
| 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)
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| 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
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| StructuralIntegrityAssociates, Inc.
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| -- u11 I _ _ __ _I__ _ _ __ _ _ I_I_
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| _ _
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| -sY-sx 60000 Q- 40000 -' A I F +/- -l + F -I I U,
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| 20000 4 --------- + -N------ F + 1 4 F F I UI 0 100 200 .300 400 500 600 700 800 900 1000 Time (sec)
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| Figure 14: Safe End Total Stress History for 50% Flow
| |
| -sy-sx 60000 40000 41 20000 I
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| 0 ____ F F F F ______
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| 2UUIU0 I F I
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| -40000
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| -60000
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| -60000 0 100 .200 300 400 500 600 700 800 900 1000 Time (sec)
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| Figure 15: Safe End Membrane Plus Bending Stress History for .50% Flow File No.: VY-16Q-305 Page 25 of 29 Revision: 0 F0306-OI RO
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| StructuralIntegrityAssociates, Inc.
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| ==
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| .=
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| 100 200 300 400 500 600 700 800 900 1000 Time (sec)
| |
| Figure 16: Safe End Total Stress History for 0% Flow 30000 Ce 100 200 300 400 500 600 700 800 900 1000 Time (sec)
| |
| Figure 17: Safe End Membrane Plus Bending Stress History for 0% Flow File No.: VY-16Q-305 Page 26 of 29 Revision: 0 F0306-01 RO
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| C StructuralIntegrity Associates, Inc.
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| 0 1000 2000 3000 4000 5000 6000 7000 8000 Time (sec)
| |
| Figure 18: Blend Radius Total Stress History for 100% Flow 40000 a
| |
| 0 1000 2000 3000 4000 5000 6000 7000 8000 Time (sec)
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| 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
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| II I
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| I I
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| 0~
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| I I
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| 0-~
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| U, I
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| I 0 1000 2000 3000 4000 Time (sec) 5000 6000 7000 8000 I
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| Figure 20: Blend Radius Total Stress History for 50% Flow I
| |
| 30000 U,
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| 0 1000 2000 3000 4000 5000 6000 7000 8000 Time (sec)
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| Figure 21: Blend Radius Membrane Plus Bending StressHistory for 50% Flow File No.: VY-16Q-305 Page 28 of 29 Revision: 0 F0306-O1RO
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| I I V StructuralIntegrityAssociates, Inc.
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| 35000 I
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| 30000 I 25000 I 20000 C.
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| U, I 15000 I 10000 I 5000 I 0 0 1000 2000 3000 4000 Time (sec) 5000 6000 7000 8000 Figure 22: Blend Radius Total Stress History for 0% Flow I 20000 _____ _____
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| I I 10000 /
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| I 5000 --- i i i i i I 0 +/- _____
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| I -5000 I -10000 0 1000 2000 3000 4000 Time (sec) 5000 6000 7000 8000 Figure 23: Blend Radius Membrane Plus Bending Stress History for 0% Flow File No.: VY-16Q-305 Page 29 of 29 Revision: 0 F0306-OI RO
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| V StructuralIntegritjAssociates, Inc.
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| APPENDIX A FINITE ELEMENT ANALYSIS FILES File No.: VY-16Q-305 Page A l of A2 Revision: 0 F0306-OI RO
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| I ,Structural Integrity Associates, Inc.
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| 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 Page A2 of A2 Revision: 0 F0306-01 RO
| |
| | |
| StructuralIntegrityAssociates, 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
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| StructuralIntegrity Associates, Inc. I I
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| Table of Contents I
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| 1.0 2.0 O B JEC TIV E ..................................................................................................................................
| |
| M ETH O D O LO G Y ..........................................................................................................................
| |
| 4 4
| |
| I 3.0 ANALYSIS .................................. ........................ 7 4.0 CALCULATION OF THERMAL STRESSES FOR TRANSIENT 9 ...................... 11 I 5.0 FATIGUE U SAG E RESULTS .............................................................................. s
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| ................. 14 6.0 ENVIRONMENTAL FATIGUE ANALYSIS ................................. . . ... I....... 14 7.0 REFE REN C ES ........................................................................................................................... 15 I
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| APPENDIX A
| |
| | |
| ==SUMMARY==
| |
| OF OUTPUT FILES .................................... ............................. Al I
| |
| List of Tables I
| |
| Table 1: Maximum Piping Stress Intensity Calculations ............................................................ 16 I
| |
| Table 2:
| |
| Table 3:
| |
| B lend R adius Transients..................................................................................................
| |
| Safe End Transients ............................................... .......
| |
| 17 18 I
| |
| Table 4: Blend Radius Stress Summary .......................................... 19 Table 5: Safe End Stress Sum m ary .....................................................................................
| |
| Fatigue Results for Blend Radius (60 Years) ...................................................................
| |
| ......... 20 I Table 6: 21 Table 7:
| |
| Table 8:
| |
| Fatigue Results for Safe End (60 Years) ...................................
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| Material Properties (For.Transient 9) .............................................................................
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| 23 25 I
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| i File No.: VY-16Q-306 Page 2 of 34 Revision: 0 F0306-01 RO
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| I I "Structural integrity , Inc.
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| Associates, 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°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 Page 3 of 34 Revision: 0 F0306-01 RO
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| StructuralIntegrityAssociates, Inc.
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| 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.
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| 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.
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| 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.
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| 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
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| *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, -
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| 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.
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| 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.
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| File No.: VY-16Q-306 Page 4 of 34 Revision: 0 F0306-01 RO 1
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| StructuralIntegrityAssociates, Inc.
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| 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.
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| The steps involved in the evaluation are as follows:
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| :
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| *
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| * Develop finite element model Develop heat transfer coefficients and boundary conditions for the finite element model Develop Green's Functions
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| :
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| e
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| *
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| . 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).
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| 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.
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| 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
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| * 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.
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| 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.
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| File No.: VY-16Q-306 Page 5 of 34 Revision: 0 F0306-OIRO
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| StructuralIntegrityAssociates, Inc.
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| 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.
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| 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]
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| calculation.
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| 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:
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| 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.
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| * 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.).
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| * Input file "TRANSNT.INP": This file contains the input transient history for all thermal transients to be analyzed for the location being evaluated.
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| 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.
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| 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.
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| 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.
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| 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.
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| The 10 transients to be analyzed are described in Reference [2], for the recirculation outlet nozzle.
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| 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
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| H structuralIntegrityAssociates, Inc.
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| 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.
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| 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.
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| 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.
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| The steps associated with this process are described in the following sub-sections.
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| 3.1 Transient Definitions (for program STRESS.EXE)
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| * The program STRESS.EXE requires the following three input files for analyzing an individual transient:
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| i GREEN.DAT. There are 12 stress history functions (Green's Functions) obtained from Reference
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| [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.
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| * GREEN.CFG is configured as described in Reference [5].
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| 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.xlsand Safe End Transients.xls,which are contained in the computer files. Transients are split into the following groups based upon flow rate:
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| * Transients 2, 3, 5, 6, 7, and 8 are run at 100% flow Green's Function
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| * Transients I and 10 are run at 50% flow Green's Function
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| * Transient 4 is run at no flow, 50% flow, and 100% flow Green's Functions, as shown in Tables 2 and 3.
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| , Transient 9 is simulated by ANSYS [11] model and the thermal results are taken from ANSYS directly. See Section 4 for details.
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| * Transients 11 and 12 have only small temperature change (70°F to 100°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.
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| I
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| * The loss of feedwater heaters (Feedwater Heater Bypass) event has a negligible temperature, change (526 'F to 516 'F) associated with it. Therefore this transient is ignored.
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| I File No.: VY-16Q-306 Page 7 of 34 Revision: 0 F0306-OIRO
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| Structural Integrity Associates, Inc.
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| 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.
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| 3.3 Pressure Load I The pressure stress associated with a 1,000 psi internal pressure was determined in Reference [1].
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| These values are as follows: I Pressure stress for the safe end:
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| * 11,350 psi membrane plus bending linearized stress intensity.
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| * 11,490 psi total stress intensity.
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| Pressure stress for the blend radius:
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| * 33,640 psi membrane plus bending linearized stress intensity.
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| * 31,300 psi total stress intensity.
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| The pressure stress intensity values for each transient were linearly scaled based on the pressure.
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| The actual pressure for column 6 of Tables 4 and 5 is obtained from Tables 2 and 3, respectively.
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| The scaled pressure stress values are shown in columns 7 and 8 of Tables 4 and 5.
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| The pressure stress is combined with the peak and valley points to calculate the final stress values used for fatigue analysis.
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| 3.4 Attached Piping Loads I Additionally, the piping stress intensity (stress caused by the attached piping) was determined.
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| These piping forces and moments are determined as shown in Figure 1.
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| 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:
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| (Mx), Mx - FL, M I For Cut1: : (My), :My + F, L, File No.: VY-16Q-306 Page 8 of 34 Revision: 0 F0306-OI RO
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| StructuralIntegrityAssociates, Inc.
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| (M.,)2 = M. -- FYL2 For Cut II:
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| (My) 2 = My + FL 2 The total bending moment and shear loads are obtained using the equations below:
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| MXYý(M. 12+ (MY) 2 For Cut I:
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| Fx,=/ (Fx), 2 +(Fy), 2 M = (M)22+(MY)2 2 For Cut II:
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| Fy (F,) 22 +(F,) 22 The distributed loads for a thin-walled cylinder are obtained using the equations below:
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| 1RNL2 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.
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| For Cut 1, using thin-walled equations:
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| (P* )z =-Pa, 2
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| tN
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| +_Nz tN (PM)v -GPaN tN qN (PM)O_ (P_)R.2 +_(r ) 2.
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| SIAX ==2 or SIMIX= 2 (P11)z 2-(PIR), + (CM ) 2 File No.: VY-16Q-306 Page 9 of 34 Revision: 0 F0306-01 RO
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| StructuralIntegrityAssociates, Inc.
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| Because pressure was considered separately in this analysis, the equations used for Cut I are valid for Cut II.
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| 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.
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| L2 The length from the end of the nozzle where the piping loads are applied to the location of interest in the blend radius.
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| 3 Mxy = The maximum bending moment in the xy plane.
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| Fyx = The maximum shear force in the xy plane.
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| = The normal force per. inch of circumference applied to the end of the nozzle in the z direction.
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| qN = The shear force per inch of circumference applied to the nozzle.
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| RN= The mid-wall nozzle radius.
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| Since. the pressure was considered separately in this analysis, the equations can be simplified as follows:
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| NZI (PM), = -3 t N
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| (PM)d = 0 rMn=q0 iN.
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| 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:
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| F, = 20,000 lbs K = 2,004,000 in-lb Fy == 30,000 F, 20,000 lbs lbs, my = 3,000,000 M,-= 2,004,000 in-lb in-lb L, is equal to 4.25 inches and the L2 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 maxmu stress stress intensities intens Ties i due due to to the th piping loads are 570889 psi at the safe end and 280.16 psi at iiglasae50.9piattesf n n 8.6pia the blend radius. The' iping load sign is set as the same as the thermal stress sign.
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| File No.: VY-16Q-306 Revision: 0 Page 10 of 34 I F0306-OI RO
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| StructuralIntegrity Associates, Inc.
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| 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.
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| 3.5 Fatigue Analysis (for program FATIGUE.EXE)
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| The number of cycles projected for the 60-year operating life is used for each transient [2]:
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| 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.
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| 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:
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| 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]
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| Design Stress Intensity 26700 psi [9] 17000 psi [9]
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| Values, Sm @ 600°F @ 600-F Elastic Modulus from 30.0x10 6 psi [13] 28.3x10 6 psi [13]
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| Applicable Fatigue Curve _ _ _ psi__13]________psi
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| _ _ __13 Elastic Modulus Used in 6 Finite Element Model. 26.7x10 psi [1] 27.0x10 6 psi [1]
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| 'The Geometric Stress 1.0 1.53 [3]
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| Concentration Factor Kt 1.0_1.53_[3]
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| The results of the fatigue analyses are presented in Tables 6 and 7 for the blend radius and safe end for 60 years, respectively.
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| The fatiguerun inputs described are contained in EXCEL files BRresults.xls and SEresults.xls, which are contained in the computer files.
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| 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.
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| An additional case was also run to simulate the uphill (RPV) side of the blend radius, where the
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| * 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
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| Structural IntegrityAssociates, 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, the material properties for 400'F are used for the blend radius, cladding and vessel. Table 8 shows I
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| the material properties at 400TF. The flow rate at this transient is 3395.2 GPM (calculated from 12%
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| of max flow rate [2]) and is shown in Tables 2 and 3.
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| 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 5000 F, h, for 3395.2 GPM (2.084 ft/s) flow is 4911 -2.084 = 672.8 BTU/hr-ft2-°F.
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| Per [4], the heat0.8transfer coefficient at 100°F, h, for 33395.2 GPM (2.084 f-t/s) flow isi 25 22'50 -(k2.85 )]° =_308.24 BTU/hr-ft2-F The fluid temperature shock is:
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| T= 526 0 F - 130°F - 526 0 F Region22 Per [4], the heat transfer coefficient at 500F, h, for 3395.2 GPM (2.084 ft/s) flow is 4911-.(2"084°8(, 25 0..2 632.21 BTU/hr-ft2 _OF.
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| Per [4], the heat transfer coefficient at 300'F, h, for 3395.2 GPM (2.084 ft/s) flow is 08 4789Q(2" 4°( 26 *0.2 4789. 2.084 0.85 ) = 616.57 BTU/hr-ft2 _-°F.
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| File No.: VY-16Q-306 Page 12 of 34 Revision: 0 F0306-OIRO
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| U Struetural IntegrityAssociates, Inc.
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| IThe fluid temperature shock is:
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| T = 5260 F - 2680 F - 5260 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-ft2 -OF.
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| Per [4], the heat transfer coefficient at 3000 F, h, for 3395.2 GPM flow is 336. 44789) 328.04 BTU/hr-ft2 -OF.
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| The fluid temperature shock is:
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| Case 1: T = 526'F - 268°F - 526 0 F Case 2: T = 526 0 F Region 4 The heat transfer coefficient, h, is 0.4 BTU/hr-ft2-OF [4].
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| The temperature is:
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| T = 120°F 4.2 Thermal Results I The flow dependent thermal load case outlined in Section 4.1 was run on the finite element model.
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| 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.
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| * The critical safe end and blend radius locations are defined in Reference [1] at nodes 6395 and 3829, respectively.
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| 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.
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| I File No.: VY-16Q-306 Page 13 of 34 Revision: 0 F0306-OI RO
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| StructuralIntegrityAssociates, Inc.
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| 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.
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| 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).
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| 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:
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| * 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.
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| * The highest pressure stresses from the FEM analysis occur in the low alloy steel nozzle forging.
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| 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.
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| 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%.
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| 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% +
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| 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.
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| 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% +
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| 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.
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| File No.: VY-16Q-306 Page 14 of 34 Revision: 0 F0306-0I RO
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| StructuralIntegrity Associates, Inc..
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| ==7.0 REFERENCES==
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| : 1. Structural Integrity Associates Calculation No. VY-16Q-305, Revision 0, "Recirculation Outlet
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| *Nozzle Green's Functions."
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| : 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.
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| : 3. CB&I, RPV Stress Report Section: S9 "Stress Analysis Recirculation Outlet Nozzle Vermont Yankee Reactor Vessel." 9-6201, SI document, VY-16Q-204.
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| : 4. CB&I, RPV Stress Report Section: T9 "Thermal Analysis Recirculation Outlet Nozzle Vermont Yankee Reactor Vessel." 9-6201, SI document, VY-16Q-204.
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| : 5. Structural Integrity Associates Calculation (Generic) No. SW-SPVF-OIQ-301, Revision 0, "STRESS.EXE, P-V.EXE, and FATIGUE.EXE Software Verification."
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| : 6. VY Drawing, 5920-06623 Rev. 0, (Hitachi, Ltd. Drawing No IOR290-127, Revision 0), "Recirc.
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| Outlet Safe End," SI File No. VY-16Q-204.
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| : 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
| |
| | |
| I V StructuralIntegrityAssociates, Inc.
| |
| I Table 1: Maximum Piping Stress Intensity Calculations I
| |
| I Blend Radius External Piping Loads Fx=
| |
| Parameters 20.00 kips Safe End External Piping Loads Fx=
| |
| Parameters Pa..00 20.00 kits.
| |
| kips I
| |
| Fy = 20.00 kips Fy =
| |
| Fz =
| |
| Mx=
| |
| 20.00 30.00 2004.00 kips kips in-kips Fz =
| |
| Mx=
| |
| 30.00 2004.00 kips in-kips I
| |
| my Mz=
| |
| OD=
| |
| 3000.00 2004.00 55.88 in-kips in-kips in my=
| |
| Mz=
| |
| OD=
| |
| 3000.00 2004.00 28.38 in-kips in-kips in I
| |
| ID=
| |
| RN=
| |
| L 37.368 23.31 42.77 in in in ID=
| |
| RN L
| |
| 25.938 13.58 4.25 in in in I
| |
| I tN = 9.25 in tN 1.22 in (M,) 2 = 1148.54 in-kips (M.), = 1919.00 in-kips (My)2 = 3855.46 in-kips (my), = 3085.00 in-kips Mxy =
| |
| Fxy =
| |
| Nz =
| |
| 4022.90.
| |
| 28.28 2.56
| |
| .
| |
| in-kips kips kips/in My =
| |
| Fxy =
| |
| Nz =
| |
| 3633.15 28.28 6.62,
| |
| .
| |
| in-kips kips kips/in I
| |
| qN= -0.20 kips/in Primary Membrane Stress Intensity PMz 0.28 ksi qN= -1.07 kips/in Primary Membrane Stress Intensity PMz = 5.43 ksi I
| |
| SImax Slmax E=
| |
| =
| |
| -0.02 0.28 280.16 J ksi ksi psi t =
| |
| Simax =
| |
| S!max = .
| |
| -0.88 5.71 5708.89 J
| |
| ksi ksi psi I
| |
| I Note: The locations for Cut I and Cut II were defined in Reference [1] for safe end and blend radius paths, respectively.
| |
| I I
| |
| I I
| |
| I File No.: VY-16Q-306 Revision: 0 Page 16 of 34 I F0306-OIRO I
| |
| | |
| ! StructuralIntegrityAssociates, 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 Hesatupat 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 0 526 1010 28294 11. Design Hydrostatic 100 50 1981 60 Cycles 10 526 10 1135 (100%)' Test 1563 (7%)
| |
| 15 526 5 1135 120 cvcles 50 30 526 15 940 12. Hydrostatic Test 100 o- -- 0 1981 1830 526 1800 940 1 Cycle 1100 " (79/6) 2250 549 420 1010 11 50 2310 549 60 1010 2311 542 1 1010 2911 542 600. 1010 2912 526 *1 1010 8912 526 6000 1010 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°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 Page 17 of 34 Revision: 0 F0306-O1RO
| |
| | |
| V Structural Integrity Associates,Inc.
| |
| I I
| |
| Table 3: Safe End Transients Transient Number
| |
| : 1. Normal Startup with Time W
| |
| 0 Temp F
| |
| 100 Time Step Pressure (psjl) 0 Flow Rate (GPM) 14147.0 Transient Number
| |
| : 6. Reactor Overpressure Time fs) 0 Tomp 526 Time Step jsJ sFf Pressure jps) 1010 Flow Rate IGPMI 28294 I
| |
| Heatup at lO0F/hr 16164 549 16164 1010 (50%)- 1 Cycle 2 526 2 1375 (100%).
| |
| 300 Cycles
| |
| : 2. Turbine Roll and Increase to Rated Power 300 Cycles 16864 0
| |
| 1 601 549 549 542 542 700 1
| |
| 600 1010 1010 1010 1010 28294 (100%)'
| |
| 32 1832 2252 2312 526 526 549 549 30 1800 420 60 940 940 1010 1010 I
| |
| 602 526 1 1010 2313 542 1 1010
| |
| : 3. Loss of Feedwater Heaters Turbine Trip 25% Power 1302 0
| |
| 1800 2100 526 526 542 542 700 1800 300 1010 1010 1010 1010 28294 (100%).
| |
| : 7. SRV Blowdown 2913 2914 3614 0
| |
| 542 526 526 526 600 700 1
| |
| 1010 1010 1010 1010 28294 I
| |
| loCycles 2460 526 360 1010 1 Cycle 600 375 600 170 (100%).
| |
| 3060 3960 4260 6060 526 542 542 526 600 900 300 1800 1010 1010 1010 1010
| |
| : 8. SCRAM Other 228 Cycles 11580 12280 15 0
| |
| 70 70 526 526 10980 700 15 50 50 1010 940 28294 (100%)'
| |
| I 6760 526 700 1010 1815 526 1800 940
| |
| : 4. Loss of Feodwater Pumps 10 Cycles 0
| |
| 3 13 233 526 526 526 300 3
| |
| 10 220 1010 1190 1135 1135 0
| |
| (0%)'
| |
| 2235 2295 2296 2356 549 549 542 542 420 60 60 1
| |
| 1010 1010 1010 1010 I
| |
| U 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 I
| |
| 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 I
| |
| 17119 526 1 1010 16224 70 9360 50 17819 526 700 1010 16924 70 700 50
| |
| : 6. Turtine Generator Tnp 0 526 1013 28294 11. Design Hydrostatic - I 100 0 1981 60 Cycles . 10 526 10 1135 (I00%)' Test 1100 (7%)'
| |
| 15 526 5 1135 120 Cycles 50 I
| |
| 30 526 15 940 12. Hydrostatic Test 100 - 50 1,981 1830 526 1800 940 I Cycle 1563 (7,%)'
| |
| 2250 549 420 1010 1 1 50 1 2310 549 60 1010 2311 542 1 1010 I
| |
| 2911 542 600 1010 2912 526 1 1010 3612 526 700 1010 Notes: 1. The instant temperature change is assumed as 1 second time step.
| |
| I
| |
| : 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 transientsin Table 2 areplotted using a 6000 second steady state increment. The difference is due to the length of the Green's Functionfor the safe end which.is shorter compared to the blend Radius. I I
| |
| I I
| |
| File No.: VY-16Q-306 Page 18 of 34 Revision: 0 F0306-O1 RO
| |
| | |
| I Structural IntegrityAssociates, Inc.
| |
| Table 4: Blend Radius Stress Summary 1 2 1 3 14 15 7 81 91 10 11 12 13 Total M+B 'Total M*8 Total Total. Number Total M+B Pressure Pressure Piping Piping Total MWe Of Transient Time Stress Stress temperature Pressure Stress Stress, Stress Stress Stress Stress Cycles
| |
| &i,,nier J*si fpsig) 1pj) F 0 0 (psi) (880i (60 years) 47 300 31613 33976.4 28113.0! 300 I
| |
| 31613 31613 33976.4 34591.7' 300 90.0 22164 31613 33976.4 34972.7, 300 1 94+301 4071 24811 .54. 33976.4 31613 35953.8! 300 366& 2435 53, 31613 33976.4 35556.0U 300 5691 3481 521 101( 33976.4 252.97541 300 252.9754 37756.9E 2977 101( 33976.4 34842.91 30C
| |
| -1 2955 101( 33976.4 34824.9f 11 1834 33976.4 33708.8!
| |
| 4425 101( 33976.4 36290.9i -U 3974.40 170E 10601 101( 33976.4 33580.8!
| |
| 6070.801 3971 2551 1i01 ( 33976.4 35836.9i -1(
| |
| 12060.00 2965 185' 521 TOM1( 31613 33976.4 34830.91 4 1 01 2465 -7031 526.00 1010 31613 33976.' 34330.9( 1(
| |
| 3 2465 -70: 526.04 119( 37247 40031.61 252.97541-252.9754 39964.9f 39075.6'ý
| |
| -70" 1135 35525.51 38181.41 252.9754 -252.9754 38243.4f 37225.42 V 969( 113! 35525.! 38181.41 158.87741 15&.8774 53982.31 48030.2f UC 1131 -232.6952 34123.80 35350.70 1c 88! 143.3538 40606.851 36609.7! 1c 101C -236.9137 101C 129.2122 13996 542.0( 101( 261.8518 17247 526.0( 101Z 252.9754 23111 2971 18551 526.0( 101C
| |
| * 31613 33976.4 252.9754 2959 101C 3161Z 252.9754 1135 2959 35525.E 252.9754 38737.481 . 40283.3E GC 2959 94C 29422 252.9754 ill 101C 31613 265.7352 3010.1( 4407 101C 31613 252.9754 8912.00 101C 31613 252.9754 6 0.00 2959 184c 526.0( 101C 31613 33976.41 252.9754 252.9754 2959 2.00 2959 2959 252.9754 32.00 252.9754 32633.98 33723.58 I 2271.50 31989.74 34537.14 29!59 1 3022.00 29631 36272-981 36808.38 8914.00 1 7 0.00 4479 4407 1 615.10 2 1 17580.00 22959 1 11 8 0.00 1849. 52E 1010 31613 33976.4 228 15.G0 279" 1849 526 940 29422 31621.61 228 2254.50 295 54E 1010 31613 33976.4 265.7352 265.7352 31989.74 34537.14 228 5_!2_ 31613 2491.20 33976.4 252.9754 252.9754 35657.98 36463.38 228 8357.00 2963ý 1851 5ý2_E 1010 31613 33976.41 252.9754 252.9754 31613 34828.96 36080.38 228 9 0 1010 35190.26 1 31613 33923.86 0.52 1010 1 1010 31613 33821.75 34963.15 28 2: 1010 1010 37405.45 -1 31613 55601.05 1 425 33385.70 34840.10 1 1010 31613 12400 2058 8791 525.8 33976.41 252.86451 33923.86 35108.26 -1 10 27671 2176 549 1010 31613 33976.4 265.7352T 34645.74 36416.14 300 6643 4158 445.775 441 13803.31 14835.241 208.469 20654.77 19201.71 300 "11988.04 9562.84 300 12180.21 8345.13 300 1802.00 11 16.64 37020.64 1698.64 12 100 1698.64 100 52595.96 0 0 100 50 15651 16821 16.643121 16.64312: .1698.64 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°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 Page 19of34 Revision: 0 F0306-01 RO
| |
| | |
| V. StructuralIntegrity Associates, Inc.
| |
| I Table 5: Safe End Stress Summary I 1 1 2 1 3 1 4 [ 6 1 G 7 8 9 10 11 13 12 I
| |
| ITtal M÷B Tot.l M÷B Total "Total Number Total M÷B Pressure Pressure Piping Total Piping .T M÷B of Transient Time Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Z Stress Cycles (psi) (GO years)
| |
| 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.
| |
| I 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.
| |
| I 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 from calculation in Table 1, 5708.89 psi*(Column 5-70°F)/(575°F -70'F).
| |
| Column 10: Same as Column 9, but for M+B stress.
| |
| I 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 20 of 34 I F0306-0I RO I
| |
| | |
| V StructuralIntegrityAssociates, Inc.
| |
| Table 6: Fatigue Itesults 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 MEM+BEND Ke Salt Napplied Nallowed U 55601. 17. 55584. 37389. 1.0.00 31227. 1.000E+00 1.951E+04 .0001.
| |
| 53822. 17 53806. 48014. 1.000 30228. 1.OOOE+01 2. 161E+04 .0005 51017. 17. 51001. 44054. 1.000 28652. 1.OOOE+01 2. 547E+04 .0004 48939. 17. 48922. 52579. 1.000 27484. 1.OOOE+00 2.894E+04 .0000 46249. 17. 46233. 48340. 1.000 25974. 1.O00E+00 3.44 E+04 .0000 40607. 17. 40590. 36593. 1.000 22803. 1.OOOE+01 5. 217E+04 ..0002 39965. 17.. 39948. 39059. 1.000 22443. 1.OOOE+01 5. 647E+04 ..0002 38737. 17. 38721. .40267. 1.000 21753. 6.OOOE+01 6.59-2E+04 .0009 38243. 17. 38227. 37209. 1.000 21476. 1.000E+01 7.025E+04 .0001 37757. 17) 37740. 37702. 1.000 21202. 7.OOOE+00 7.486E+04 .000~1 37757. 476. 37281. 37314. 1.000 20945. 2.930E+02 7. 954E+04 .0037 36291. 476. 35815. 36492. 1.000 20121. 7.OOOE+00 9. 705E+04 .0001 36291. 1582. 34709. 35198. 1.000 19500. 3.OOOE+00 1. 096E+05 .00900 36273. 1582. 34691. 35110.. 1.000 19490. 6.OOOE+01 1.098E+05 .0005 36273. 1582. 34691. 35110. 1.000 19490. 1.0.00E+00 1.098E+05 ..0000 35954 1582. 34372. 35021. 1.000 19310. 5.600E+01 1. 135E+05 .0005 35954. 1582
| |
| * 34372. 35021. 1.000 19310. 1.000E+00 1. 135E+05 .00090 35954. 1582 34372. 35021 1.000 19310. 1.000E+00 1. 135E+05 .0000 35954. 1844. 34110. 34858. 1.000 19163. 1.OOOE+00 1. 167E+05 .0000 35954. 1926. 34028. 34917. 1.000 19117. 2.410E+02 1. 177E+05 .0020 35837. 1926. 33911. 34978. 1.000 19051. 1.OOOE+01 i. 191E+05 .0001 35658. 1926. 33732. 34661. 1.000 18951. 4.900E+01 1.2:14E+05 .0004 35658. 11988. 23670. 26901. 1.000 13298. 1.790E+02 5. 728E+05 .0003 35556. 11988. 23568. .27109. 1.000 13240. 1.210E+02 5.955E+05 .0002 35556. 12180. 23376. 28326. 1.000 13133. 1.790E+02 6.4 11E+05 .0003 35279. 12180. 23099. 27958. 1.000 12977. 1.000E+01 7.138E+05 .0000 34973. 12180. 22793. 27831. 1.000 12805. 1.11OE+02 8.050E+05 .0001 34973. 20655. 14318. 16974. 1.000 8044. 1.890E+02 7. 421E+07 .0000 34843. 20655. 1418.8. 16887. 1.000 7971. 1.110E+02 7.983E+07 .0000 34843. 25750. 9093. 17221. 1.000 5108. 1.OOOE+00 1.OOOE+20 ..0000 34843. 27368. 7475. 5178. 1.000 4199. 1.OOOE+01 1.OOOE+20 .0000 34843. 28113. 6730. 3789. 1.000 3781. 1.780E+02 1.OOOE+20 .0000 34837. 28113. 6.724. 3785. 1.000 3777. 1.000E+01 1. OOOE+20 .0000 34834. 28113. 6721. 3784. 1.000 3776 6.000E+01 1.000E+20 .0000 34834. 28113. 6721. 3784. 1.000 3776 1.0OOE+00 1. OOOE+20 .0000 34831. 28113. 6718. 3782. 1.000 3774 1.000E+01 1. 000E+20 .0000 34829. 28113. 6716. 3781. 1.000 3773. 4.100E+01 1. OOOE+20 .0000~
| |
| 34829. 29216. 5613. 1808. 1.000 *3153 1.000E+01 1. 000E+20 .0000 34829. 31990. 2839. 1543. 1.000 1595. 6.000E+01 1. OOOE+20 .0000 34829. 31990. 2839. 1543. 1.000 1595. 1.000E+00 1. 000E+20 .0000 34829. 31990. 2839. 1543. 1.000 1595. 1.160E+02 1.000E+20 .0000 34825. 31990. 2835. 1541. 1.000 1593. 1.000E+01 1. OOOE+20 .0000 34825. 31990. 2835. 1541. 1.000 1593. 6.OOOE+01 1.000E+20 .0000 File No.: V. Y-16Q-306 Page 21 of 34 Revision: 0 F0306-01 RO
| |
| | |
| StructuralIntegrityAssociates, Inc.
| |
| 34825.
| |
| 34825.
| |
| 31990.
| |
| 31990.
| |
| 2835.
| |
| 2835.
| |
| 1541.
| |
| 1541.
| |
| 1.000 1.000 1593.
| |
| 1593.
| |
| : 1. O00.E+00
| |
| : 1. OOOE+00 1.OOE+20 1.OOOE+20
| |
| .0000
| |
| .0000 I
| |
| 34825.
| |
| 34825.
| |
| 34825.
| |
| 31990.
| |
| 32634.
| |
| 32634.
| |
| 2835.
| |
| 2191; 2191.
| |
| 1541.
| |
| 2355.
| |
| 2355.
| |
| 1.000 1.000 1.000 1593.
| |
| 1231.
| |
| 1231.
| |
| 4 .OOOE+01
| |
| : 6. OOOE+01
| |
| : 1. OOOE+00 1.OOOE+20 1.OOOE+20 1.OOOE+20
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 34825. 32634. 2191 2355. 1.000 1231. 1.270E+02 1.00OE+20 .0000 34646.
| |
| 34646.
| |
| 34646.
| |
| 32634.
| |
| 33386.
| |
| 33581.
| |
| 2012 1260 1065 2695.
| |
| 1578.
| |
| 1120.
| |
| 1.000 1.000 1.000 1130.
| |
| 708.
| |
| 598.
| |
| 1.010E+02
| |
| : 1. OOOE+00 1.OOOE+01
| |
| : 1. OOOE+20 1.00OE+20 1.OOOE+20
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 33709. 1.000 526. 1. OOOE+01 1. OOOE+20 .0000 I
| |
| 34646. 937 1137.
| |
| 34646. 33822. 824 1455. 1.000 463. 1.OOOE+00 1. OOOE+20 .0000 34646. 33924. 722. 1228. 1.000 406. 1.OOOE+00 1.000E+20 .0000 34646. 33924. 722. 1310. 1.000 406. 1. OOOE+00 1.O00E+20 .0000 34646.
| |
| 34646.
| |
| 34646.
| |
| 34124.
| |
| 34331.
| |
| 34447.
| |
| 522.
| |
| 315.
| |
| 199.
| |
| 1067.
| |
| 3398.
| |
| -603.
| |
| 1.000 1.000 1.000 293.
| |
| 177.
| |
| 112.
| |
| 1.OOOE+01 1.OOOE+01 1.200E+02 1.OOOE+20 1.OOOE+20 1.000E+20
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 34646. 34592. 54. -130. 1.000 30. 3. 500E+01 1. OOOE+20 .0000 TOTAL USAGE FACTOR = .0108 I I
| |
| I I
| |
| I I
| |
| I I
| |
| I I
| |
| I File No.: VY-16Q-306 Revision: 0 Page 22 of 34 I F0306-0I RO I
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| | |
| StructuralIntegrityAssociates, Inc.
| |
| II Table 7: Fatigue Results for Safe End (60 Years).
| |
| LOCATIC N = LOCATION NO. 1 -- SAFE END FATIGUE C URVTE = 2 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL) m = 1.7 n= .3 S m 17000. psi Ecurv e 2.830E+07 psi Eanalysi s= 2.700E+07 psi K*t = 1.53 MAX MIN RANGE MEM+BEND Ke Salt Napplied Nallowed U 82580. -7469. 90049. 66991. 2.045 134573. 1. OOOE+00 6. 765E+02 .0015 31546. -7469. 39015. 33.281. 1..000 29691. 9. OOOE+00 6. 857E+05 .0000 31546. -5010. 36556. 28040. 1..000 26947. 1. OOOE+00 1. 160E+06 .0000
| |
| .25988. -2934. 28922. *24217. 1.000. 21884. 1. OOOE+01 2. 383E+06 .0000 2.5730. -2934. 28664. 23354. 1.000 21509. 1.OOOE+01 2. 566E+06 .0000 18521. -2934. 21455. 9572. 1.000 13903.1 .2.280E+02 9.-710E+08 .0000 18298. -2934. 21232. 21370. 1.000 17063. 1. OOOE+00 7. 876E+06 .0000 17956. -2*934. 20890. 9197. 1.000 13502. 5. 100E+01 1. OOOE+20 .0000 17956. -2741. 20697. 8846.. 1.0.00 13304. 1. 000E+00 1.OOOE+20 .0000 17956. -1264. 19220. 7194. 1..000 12071. 2.480E+02 1.000E+20 .0000 17952.. -1264. 19216. 7191. 1.000 12068. 1.OOOE+01 1.OOOE+20 .0000 17948. -1264. 19212. 7189. 1.000 12065. 4.200E+01 1.000E+20 .0000 17948. -157. 18104. 6096. 1.000 11181. 1. 800E+0i 1.OOOE+20 .0000 17948. -157. 18104. 6096. 1.000 11181. 1.OOOE+00 1.000E+20 .0000 13174. -157. 13331. 10909. 1.000 10016. 1.OOOE+00 1. OOOE+20 .0000 12978. -157. 13135. 13020. 1.000 10500. 1.200E+02 1.OOOE+20 .0000 6956. -157. 7112. 7125. 1.000 5706. 1.00OE+00 1 .OOOE+20 .0000 5393. -157. 5550. -1219. 1.000 2570. 1. 590E+02 1.OOOE+20 .0000 5393. -133. 5526. -1293. 1.000 2537. 1. OOOE+00 1.OOOE+20 .0000 5393. 136. 5258. -2126. 1.000 2165. 6. OOOE+01 1.000E+20 0000 5393. 136. 5258. -2126. 1.000 2165. 1. OOOE+00 1.000E+20 .0000 5393. 136. 5258. -2126. 1.000 2165. 7. 900E+01 1. OOOE+2ý0 .0000 4762. 136. 4626. 3924. 1.000 3514. 1. OOOE+01 1. OOOE+20 .0000 4605. 136 4469. 3153. 1.000 3218. 1. 390E+02 1.000E+20 .0000 4605. 339 4266. 3526. 1.000 3215. 1.200E+02 1.OOOE+20 .0000 4605. 909 3697. 3332. 1.000 2863. 4. 100E+01 1. 000E+20 .0000
| |
| .4518 909 3609. 3576. 1.000 2885. 1. OOOE+01 1.OOOE+20 .0000 4198. 909. 3290. 3673. 1.000 2744. 6. OOOE+01 1.OOOE+20 .0000 4130. 909. 3222. 3479.. 1.000 2655. 1.OOOE+01 1. OOOE+20 .0000 3911. 909. 3003. 2870. 1. 000 2371. 1. OOOE+01 1. 00.OE+20 .0000 3486. 909. 2578. 2947. 1.000 2170. 1.OOOE+00 1.OOOE+20 .0000 3485. 909. 2577. 2942. 1. 000 2168. 1. OOOE+00 1.OOOE+20 .0000 3419. 909. 2511. 3179. 1. 000 2199. 1. OOOE+01 1.OOOE+20
| |
| .0000 3292. 909. 2384. 2472. 1.000 1936. 6. OOOE+01 1. OOOE+20
| |
| .0000 3292. 909. 2384. 2472. 1.000 1936. 1. OOOE+00 1. OOOE+20
| |
| .0000 3292. 909. 2384. 2472. 1. 000 1936. 9. 600E+01 1.OOOE+20
| |
| .0000 3292. 914. 2378. 2098. 1.000 1829. 1. 200E+02 1. OOOE+20
| |
| ..0000 3292. 914. 2378. 2098. 1.000 1829. 1. OOOE+00 1. OOOE+20
| |
| .0000 3292. 914. 2378. 2098. 1.000 1829. 1.OOOE+00 1. OOOE+20 3292. 1029. 2264. 2247. 1.000 1810. 1. OOOE+00 1.OOOE+20 .0000 3292. 1376. 1916. 1389. 1.000 1390. 9. OOOE+00 1. OOOE+20 .0000 3135. 1376. 1759. 1452. 1.000 1325. 1.OOOE+01 1.OOOE+20 .0000 3086.
| |
| 1376. 1710. 1361. 1.000 1274. 2. 280E+02 1.000E+20 .0000 File No.: VY-16Q-306 Page 23 of 34 Revision: 0 F0306-O IRO
| |
| | |
| StructuralIntegrityAssociates, Inc.
| |
| 2809.
| |
| 2783.
| |
| 1376.
| |
| 1376.
| |
| 1433.
| |
| 1407.
| |
| 1091.
| |
| 1.187.
| |
| .1.000 1.000 1054.
| |
| 1067.
| |
| : 1. OOOE+01
| |
| : 4. 300E+01 1.000E+20 1.000E+20
| |
| .0000
| |
| .0000 I
| |
| 2783.
| |
| 2783.
| |
| 2783.
| |
| 1732.
| |
| 1793.
| |
| 1958.
| |
| 1051.
| |
| 990.
| |
| 825.
| |
| 860.
| |
| 208.
| |
| 811.
| |
| 1.000 1.000 1.000 790.
| |
| 576.
| |
| 658.
| |
| 1.000E+01
| |
| : 1. 000E+01 6.OOOE+01 1.000E+20 1.000E+20 1.000E+20
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 2783. 1958. 825. 811. 1.000 658. 1. OOOE+00 1.000E+20 .0000 2783.
| |
| 2780.
| |
| 2780.
| |
| 1958.
| |
| 1958.
| |
| 2104.
| |
| 825.
| |
| 822.
| |
| 676.
| |
| 811.
| |
| 808.
| |
| 576.
| |
| 1.000 1.000 1.000 658.
| |
| 655.
| |
| 514.
| |
| : 1. 040E+02 1.240E+02 1.000E+01 1.000E+20 1.000E+20 1.000E+20
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 416. 1.000 340. 1. 660E+02 1.000E+20 0000 I
| |
| 2780. 2352.- 428.
| |
| 2780. 2352. 428. 416. 1.000 340. 1.000E+01 1.000E+20 .0000 2780. 2352. 428. 416. 1.000 340. 6.000E+01 1.000E+20 .0000 2780. 2352. 428. 416. 1.000 340. 1.000E+00 1. OOOE+20 .0000 2763.
| |
| 2762.
| |
| 2762.
| |
| 2352.
| |
| 2352.
| |
| 2352.
| |
| 411.
| |
| 410.
| |
| 410.
| |
| 403.
| |
| 403.
| |
| 403.
| |
| 1.000 1.000 1.000 327.
| |
| 327.
| |
| 327.
| |
| 1.000E+01
| |
| : 1. OOOE+01
| |
| : 4. 300E+01 1.000E+20 1.000E+20 1.000E+20
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 2762. 2441. 321. 443. 1.000 291. 1.700E+01 1.000E+20 .0000 2762.
| |
| 2762.
| |
| 2762.
| |
| 2441.
| |
| 2441.
| |
| 2441.
| |
| 321.
| |
| 321.
| |
| 321.
| |
| 443.
| |
| 443.
| |
| 443.
| |
| 1.000 1.000 1.000 291.
| |
| 291.
| |
| 291.
| |
| 1.000E+00
| |
| : 1. 000E+00
| |
| : 2. 28E+02 1 .000E+20 1.000E+20 1.000E+20
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| .0000 2496.
| |
| 2496.
| |
| 2491.
| |
| 2441.
| |
| 2445.
| |
| 2445.
| |
| 55.
| |
| 51.
| |
| 46.
| |
| 177.
| |
| 181.
| |
| 178.
| |
| 1.000 1.000 1.000 78.
| |
| 77.
| |
| 74.
| |
| 5, 300E+01
| |
| : 2. 470E+02 1.000E+01 1.000E+20 1.000E+20 1.000E+20
| |
| .0000
| |
| .0000 I
| |
| 2487. 2445. 42. 175. 1.000 71. 4. 300E+01 1.000E+20 .0000 2487. 2487. 0. 0. 1.000 0. 1.700E+01 1.000E+20 TOTAL USAGE FACTOR
| |
| .0000
| |
| .0015 I
| |
| I I
| |
| I I
| |
| I I
| |
| I I
| |
| File No.: VY-16Q-306 Revision: 0 Page 24 of 34 I F0306-01 RO I
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| StructuralIntegrityAssociates, Inc.
| |
| Table 8: Material Properties (For Transient 9)(1)
| |
| SA-533 Gr B SA-508 Cl 2 SA-240 SA-182 F316
| |
| @400 OF @400 'F Type 304 @300 OF Material (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 8.0 7.7 10.2 9.8 Expansion, e-6, in/in/°F Thermal Conductivity, 23.1 23.1 10.4 9.3 Btu/hr-ft-°F Thermal Diffusivity, ft 2/hr 0.378 0.378 0.165 0.150 Specific Heat, Btu/Ib-°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 Page 25 of 34 Revision: 0 F0306-01 RO
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| StructuralIntegrityAssociates, Inc.
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| F,,
| |
| Figure 1: External Forces and Moments on the Recirculation Outlet Nozzle File No.: VY-16Q-306 Page 26 of 34 Revision: 0 F0306-OIRO
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| V StructuralIntegrityAssociates, Inc.
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| AREAS K IMN Nti APR 19 2007 M.AT 13:35:14 Region 3 Region 4 I
| |
| Region 2
| |
| * / Region I Transition Regions x
| |
| =*Jz 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 Page 27 of 34 Revision: 0 F0306-O I RO
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| StructuralIntegrityAssociates, Inc. ]
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| (psig)
| |
| Pressure
| |
| *--
| |
| ('F)
| |
| [*Temp I-Temp (-F) - -Pressure (psig)j 600 1100 1050 1000 950 500 900 400 0) 0.,
| |
| 200 1001 0 3000 6000 9000 12000 15000 Time (seconds)
| |
| Figure 3: Transient 1 - Normal Startup at 100°F/hr
| |
| [-Temp f) -- Pressure I 555 1120 1040 550 960 880 545 800 720 540 640
| |
| -560 IL E 535 -480 400 530 320 240 525 160
| |
| -80 520 0 0 50 100 150 200 250 300 350 400 450 500 Time (seconds)
| |
| Figure 4: Transient 2 - Turbine Roll and Increase to Rated Power File No.: VY-16Q-306 Page .28 of 34 Revision: 0 F0306-OI RO
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| StructuralIntegrity Associates, Inc.
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| I I- Temp (F) - ,-- Pressure (psig) 600 1 1080 1040 550 1000 960
| |
| . 920 500 -
| |
| -880
| |
| - 840 450 . 800
| |
| - 760 400 - 720
| |
| . 680
| |
| .640
| |
| -3 5 0
| |
| .600 *
| |
| - 560
| |
| * 300 -520 480
| |
| : 4. 250 440 a-400 200 360 320
| |
| .280 150
| |
| . 240 200 100 160 120 50 80 40 0
| |
| 0 2000 4000 6000 8000 10000 Time (seconds)
| |
| Figure 5: Transient 3 - Loss of Feedwater Heaters and Turbine Trip 25% Power
| |
| [- Temp (-F) - - Pressure (psig) 600 1280 1240 1200 1160 500 1120 1080 1040 1000 960 920 880 400 80
| |
| / tOO 760 a,
| |
| / 7320 a.
| |
| 680 300 640 600 560 a-520
| |
| / -480 f 440 200 / 400 360 320
| |
| \\ ,/ 280 240 100 *200
| |
| -160
| |
| ,*120 2]-80 S40 0 0 0 2000 4000 6000 6000 10000 12000 14000 16000 18000 20000 22000 Time (seconds)
| |
| Figure,6: Transient 4 -Loss of Feedwater Pumps File No.: VY-16Q-306 Page 29 of 34 Revision: 0 F0306-O1 RO
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| StructuralIntegrityAssociates, Inc.
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| I- Temp (F) - - Pressure (psig) I 555 1200 1150 1100 1050 550 I --- 1000 950 900 545 850 800 750 700 "
| |
| 540 650
| |
| --600 E
| |
| - 550 =
| |
| E 535 - 500* C I-
| |
| - 450
| |
| -400 530 -350 300 250 200 525 150 100 50 520 0 0 500 1000 1500 2000 2500
| |
| * 3000 Time (seconds)
| |
| Figure 7: Transient 5 - Turbine Generator Trip
| |
| -Temp (f) - -Pressure (psig) 600 1500 I1400 S1300 1200 1100 500 .. - -" - - - 1000 00 8
| |
| * 700 600 400 5o00 400 300
| |
| -200 100 300 0 0 500 1000 1500 2000 2500 30 00 Time (seconds)
| |
| Figure 8: Transient 6 - Reactor Overpressure File No.: VY-16Q-306 Page 30 of 34 Revision: 0 F0306-01 RO
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| | |
| .
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| V StructuralIntegrityAssociates, Inc.
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| I 600 -Temp (°F) - - Pressure (psig) 1100 4-1000 500 0 9O 800 700 600 a-E II 500 I--
| |
| I 400 I
| |
| 300 200 100-100 2000 4000 6000 8000 10000 12000 Time (seconds)
| |
| Figure 9: Transient 7 - SRV Blowdown I--Temp (*F) - -Pressure (psig) I 600 1100 1000 l
| |
| 500 900 800 400
| |
| -700
| |
| -600 300 Soo E
| |
| .400 200 300 200 100 100 0 0 0 1000 2000 3000 4000 5000 Time (seconds)
| |
| Figure 10: Transient 8 - SCRAM Other File No.: VY-16Q-306 Page 31 of 34 Revision: 0 F0306-OlRO
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| StructuralIntegrity Associates, Inc.
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| 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- .
| |
| -
| |
| .*
| |
| 300 -
| |
| ooo6 600 I 200
| |
| * 400I 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
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| | |
| StructuralIntegrity Associates, Inc.
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| 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 Page 33 of 34 Revision: 0 F0306-01 RO
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| V StructuralIntegrityAssociates, Inc.
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| 11250.
| |
| Tbm me:
| |
| I.
| |
| ,tS" o
| |
| -to Lm 0.::iOZOO]
| |
| " .. 64W 00 100M Iwo 1ZW140 0 0W Z1UG.
| |
| Figure 14: Typical Stress Response Using Green's Functions File No.: VY-16Q-306 Page 34 of 34 Revision: 0 F0306-01 RO
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| | |
| I StructuralIntegrityAssociates, Inc.
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| 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 Page Al of Al Revision: 0 F0306-OI RO
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| | |
| StructuralIntegrity 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
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| V StructuralIntegrityAssociates, Inc.
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| I I
| |
| Table of Contents I
| |
| 1.0 O B JE C TIV E ............................... ................................................................................. ... 3 2.0 M ET H O D O LO G Y ...................................................
| |
| 2.1
| |
| ...................................................................
| |
| B ackground ............................................................................................ ...............................
| |
| 3 3 I 2.2 Design Transients and Fatigue Analysis ................................... 4 3.0 4.0 ASSUM PTIONS/DESIGN INPUTS ...........................................................................................
| |
| ANALYSIS ..........................................................
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| 4 12 I
| |
| 5.0 6.0 RESU LTS O F AN A LY SIS ...................................................................................................
| |
| REFERENCES .......................................................
| |
| 14 15 I
| |
| APPENDIX A PIPESTRESS INPUT FILES .............................................................................. Al APPENDIX B PIPESTRESS OUTPUT ...................................................................................... BI 1 I
| |
| List of Tables I
| |
| Table 1: Material Properties [1] [3]......................... ....................... 6 Table 2: Recirculation and RHR Piping Segment Numbers ............................................... ............... 7 Table 3: VY Thermal Transients ..................................................................... 9 I
| |
| 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
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| I I
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| File No.: VY-16Q-307 Revision: 0 Page 2 of 16 I F0306-01RO I
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| V StructuralintegrityAssociates, Inc.
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| 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 Page 3 of 16 Revision: 0 F0306-O1RO
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| | |
| Structural IntegrityAssociates, 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 pressures were updated to account for EPU [9].
| |
| 3 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), AT2 (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]ý 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
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| [1]. The 1998 Edition of Section III (with 2000 Addenda) has been accepted by the US NRC for use I
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| 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.
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| 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 piping support information was obtained from plant drawings [ 15]. The pipe size, schedule, I
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| 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.
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| !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
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| File No.: VY-16Q-307 Page 4 of16 i Revision: 0 F0306-O1RO I
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| HI StructuralIntegrity Associates, Inc.
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| 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 hr ý47.45-bm)
| |
| (7.48gal(
| |
| f F3 hr 60mi J 32,36gpm U Where flow is stopped, a flow rate that gives an equivalent natural convection heat transfer coefficient is calculated.
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| 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.
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| 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.
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| I I
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| File No.: VY-16Q-307 . Page 5 of 16 Revision: 0 F0306-O1RO
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| V StructuralIntegrityAssociates, Inc. -
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| I Table 1: Material Properties [11 [3]
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| ASTM A-106 Grade B (C-Si)
| |
| Coefficient of Linear Mean Coefficient Design I
| |
| Young's Thermal Thermal Thermal of Thermal Stress Yield Temperature
| |
| ( 0 F) 70 Modulus (xl0 6 psi) 29.5 Conductivity (Btu/hr-fl-°F) 27.5 Diffusivity (ft2/hr) 0.529 Expansion.
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| (in/100 ft) 0.00 Expansion (10-6
| |
| /in/in./F) 6.40 Intensity Strength (ksi) 20.0 (ksi) 35.0 I
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| 100 29.3 27.6 0.512 0.20 20.0 35.0 200 300 400 28.8 28.3 27.7 27.6 .
| |
| 27.2 26.7 0.486 0.453
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| .0.428 1.00 1.90 2.80 20.0 20.0 20.0 32.1 31.0 29.9 I
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| 500 27.3 25.9 0.398 3.70 18.9 28.5 600 26.7 25.0 0.374 4.70 ASME SA-376 TP 316 (l6Cr-12Ni-2Mo) 17.3 26.8 I
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| Coefficient of Temperature Young's Modulus Thermal Conductivity Thermal Diffusivity Linear Thermal Expansion Mean Coefficient of Thermal Expansion (10-6 Design Stress Yield Intensity Strength I
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| (0 F) (x10 6 psi) (Btu/hr-fl-°F) (ft2/hr) . (in/] 00 ft) /in/in/-F) (ksi) (ksi) 70 100 200 28.3 28.1 27.6 8.2 8.3 *
| |
| .8.8 0.139 0.140 0.145 0.00 0.30 1.40 8.50 20.0 20.0 20.0 30.0 30.0
| |
| .25.9 I
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| 300 27.0 . 9.3 0.150 2.50 20.0 23.4.
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| 400.
| |
| 500 600 26.5 25.8 25.3 9.8 10.2 10.7 0.155 0.160 0.165 3.70 5.00 6.30 19.3 18.0 17.0 21.4 20.0 18.9 I
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| ASME SA-403 WP 316 (16Cr-12Ni-2Mo)
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| Coefficient of Lineai Mean Coefficient Design I
| |
| Young's Thermal Thermal Thermal of Thermal Stress Yield Temperature (TF) 70 Modulus (x 106 psi) 28.3 Conductivity (Btulhr-fl-0 F) 8.2 Diffusivity (ft2/hr) 0139 Expansion (inilO0 ft) 0.00 Expansion (10-6
| |
| /iniini0 F) 8.50 Intensity Strength (ksi) 20.0 (ksi) 30.0 I
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| 100 . 28.1 8.3 0.140 0.30 20.0 30.0 200 300 400
| |
| *27.6 27 26.5 8.8 9.3.
| |
| 9.8 0.145 0.150 0.155 1.40 2.50 3.70 20.0 20.0 18.7 25.9 23.4 21.4 I
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| 500 25.8 10.2 0.160 5.00 17.5 20.0 600 25.3 10.7 0.165 6.30 The materialpropertiesapplied in the analyses are taken from ASME Section II PartD 1998 Edition with 2000 16.4 18.9 I
| |
| 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 originaldesign code is acceptable since later editions typically reflect more accurate materialpropertiesthan was published in prior I
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| Code editions.
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| I I
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| I File No.: VY-16Q-307 Revision: 0 Page 6 of 16 I F0306-O1RO I
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| U StructuralIntegrityAssociates, Inc.
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| 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
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| *Only applicable for RHR initiation File No.: VY-16Q-307 Page 7 of 16 Revision: 0 F0306-0I RO
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| | |
| I
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| *StructuralIntegrityAssociates, inc.
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| V I
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| .04'.
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| Figure 1. Recirculation and RHR Piping Diagram I File No.: VY-16Q-307 Revision: 0 I I
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| I I
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| I I
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| V StructuralIntegrityAssociates, Inc.
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| Table 3: VY Thermal Transients*
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| 1 1 __________ TlseooThCondidioan 141171(8j [z] Peo No.
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| TC.n7enl Dewdptk"I Pipiog Opo. 1 T- T_ I Ti-o R F"ow j ..... I o"l °'o l IC.w J I Regk,7n (iF0 [ () I (s.) I ('F ) FTemp.('8)] 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 45 00 70 00 800 60 905 0 1.100 70 100 1800 60 452 0 1,100 Desigo Hlydeosess 5 Z00 (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 50 1 402 I,000 5 00 00 0s90
| |
| :00 2 Design Hy&. 0 452 1.100 50 60 6 100 100 100 1800 2 (Lek T..)'- 50 0 0 1,100 1000 00 100 1800 7A 120 50 1800 0 0 100 100 100 78 8 0 IO0 100 0000 0 0 1000 0 9A 100 100 100 1800 0 0 1,100 5o 0 0 1.100 50 1 .100 I0 10 1800 9B 1 00 s1010 I 549 00 4 16164 10 2 549 100 549 16164 100 16,158 50 1,010 100 040 16164 100 16,158 50 1,035 3 040 549 100 549 16164 :00 6.463 500 1.035 4
| |
| 549 16164 100 3.232 50 1.035 5 549 100 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 50 . 1.035 1.035 549 16164 t00 0 9A 549 100 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 10Ra6ed 542 049 542 0 STEP 6.463 1.055 1.035 290 4Poo* +SCRAM 6
| |
| - 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 2035 1.035 1,035 1,035 0 STEP 12,926 4 026 542 526 1.035 542 526 0 STEP 6.463 1,035 T1-l- t'Ro& 5 526 5 onrease solRoted STEP 6,463 1.035 1.005
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| ,3
| |
| * 290 65 526 542 526 "6 0 0 SE .6 Po5 +SCA 1 4 Pow-- SCRAM
| |
| -2 7A 526 542 . 526 0 STEP 358 1,010 1,010 740 I50 I50 1 0 STEP
| |
| * 0 120 120 8 026 542 5266 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 32.316 1,010 1,010 1,010 1,0 542 900 64 2 542 526 3 542 526 542 900 64 32,316 1,035 1,035 900 64 12.926 1,035 1,O35 4 302 526 542 1.035 1,035 900 64 6,463 5 542 526 542 Loss of 64 . 6,463 1.035 1,035 5x'2 6 542 526 542 900 6 Peedoolere Iaree, TurbiseTrip(4-) 7A 542 526 042 900 64 358 1,010 . 1,010 ISO I50 10 900 0 0 120 120 76 542 526 542 900 64 330 1.035 1,035 8
| |
| 542 526 542 900 64 5I 1.035 1,033 9A 150 150 150 900 60 0 1,035 1,005 9B 526 542 326 360 160 32,316 1.010 12010 I
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| 526 542 026 360 160 32,316 -- ,015 1.0LO 2
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| 526 542 526 360 160 32,316 10035 1,035 3
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| 526 042 526 360 160 12.26 1,035 1,035 4
| |
| 026 542 526 360 160 6.463 1,035 1.035 Less of S 542 526 360 160 6,463 1.030 1.035 5 2 7 Feedwate leisee 6 '26 526 542 526 360 160 356 1,010 1,010 Tobine Tip (-) 7A I50 I50 I50 360 0 6 120 120 7B 526 542 526 360 160 335 1,035 ,035 4
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| 526 542 526 360 160 5164 1,035 1,035 7A 150 520 00 360 0 0 1,005 1,030 971 File No.: VY-16Q-307 Page 9 of 16 Revision: 0 F0306-O1RO
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| | |
| I VStructuralIntegrityAssociates, Inc.
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| I Table 3: VY Thermal Transients (continued)
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| Thermal Conditi-os [41[71 189[10 T
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| I I
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| [1 N:.
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| Tnss.s, D-Hf..nln "Pi..g j Op".r. TTn.
| |
| T. Rl m 3 IniMul r.I f CR.go. J p. F3 (OF) (se.) (ýFsr) (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 I
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| 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, Hmaat 6 $16 526 536 0 STEP 6,463' 1,035 1,035 35 P40431PWIi-,SE STEP 351 001e 1.010 1,030 Bypass(- 7A 516 326 516 0 7B 3 1So 50 So 10 0 STEP 0 IN 120 9A 9B 8
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| I 516 516 ISO 526 526 526 150 516 516 516 150 526 0
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| 0 0
| |
| 0 STEP STEP STEP STEP 335 502 0
| |
| 32,316 1.035 1.035
| |
| * 1.035 1,010 1.010 1.035
| |
| ,035 1,035 I.m10 1,010 1 I 2 526 516 526 0 STEP 32,316 32,336 3.035 1.035 I
| |
| 3 526 516 526 0 STEP 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 Partial FWHeaer Fdw H-.t 6 526 5"16 526 0 STEP 6.463 1.035 1.035 35 526 536 526 0 STEP 351 1,010 1.010 Bypass ( 7 7A 7B 150 150 150 0 STEP 0 120 120 9A 9B 8
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| 2 I
| |
| 526 526 150 300 300 516 516 150 526 526 526 526 150
| |
| $00 300 0
| |
| 0 0
| |
| 220 220 STEP STEP STEP 3698 3698 335 502 0
| |
| 600 600 1,035 1035 1,035
| |
| ,:190 1,190 1.035 1.035 1,035 I,135 1.135 I
| |
| 3 300 526 30$ 220 3698 600 1.213 1.160 30 Loss of FoedwaterPumps o(03o0 Vals-Cl.ol I" step down
| |
| 'A 7B 4
| |
| 5 6
| |
| 300 300 300 300 I50 s
| |
| 526 526 526 520 50 300 300 300 300 13$
| |
| 220 220 220 220 0.03 3698 3698 3693 3693 0
| |
| 400 200 200 306 0
| |
| 1.213 1.215 1.215 1.$90 120 13,60 1.:60 6
| |
| 1.160 1,135 120 I
| |
| 3698 6 1.215 1.160 I
| |
| 8 300 326 30$ 22$
| |
| 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 Feod wate,P uops (Imlaon Vatv-Close) IsI & 2.d stop o 4
| |
| 6 7A 71 5
| |
| 500 500 500 500 50.
| |
| 300 300 300 300 I350 0
| |
| 500 500 500 150 13980 1980 1980 1980 0.01 364 364 364 364 0
| |
| 400 200
| |
| * 200 301 0
| |
| .
| |
| 910 9$0 910 885 120 1,160 1.160 1.160 1.135 120 5X 2 I 910 1.160" I
| |
| 8 500 $00 500 1980 364 6 9A 500 300 500 3980 364 429 910 1.160 9B 15$. 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 12 Loss of Feedoaler Pumps (Isolaion ValvM Close) 2nd & 3,e stIpdown 7A 7B 4
| |
| 5 6
| |
| 300 300 300
| |
| $00' 150
| |
| .500 500 500 500 150 300 300 300
| |
| $30 150 180 180 180 10 0.01 4000 4000 4000 4000 0
| |
| 400 200 200 301 0
| |
| ,1360
| |
| .160 1.160 1.135 120 700 700 700 675 121 5X2 I 8 300 500 300 100 4000 69 1,00 700 9A 90 I
| |
| 2 300 150 349 549 500 150 300 300 300 150 549 549 180 0.01 8964 8964 4000 0
| |
| 0.10 100 429 0
| |
| 16.130 16,150 1,160 1,160 240 540 700 700 1.010 1.010 I
| |
| 5349 $00 549 8964 300 16358 265 1.,035 I
| |
| "549 $00 549 964 100 6.463 265 1.035 Loss of 4 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 330 10 150 8964 100 0 120 120 0 549 300 549 8%4 100 168 265 1,035 9A 9B3 2
| |
| * 549 150 5349 549 300 150 526 576 549 150 549 549 8964 8967 0
| |
| 0 100 300 STEP STEP 443 0
| |
| 32.316 32,316 265 265 1.010 13010 1.035 1.035 1,010
| |
| -1.010 I
| |
| 3 549 526 549 0 sTEP S 32.316 1.035 1.035 I
| |
| 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 I
| |
| 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 Pg10o16 File No.: VY-16Q-307 Revision: 0 F0306-01IRO I
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| | |
| I Structural IntegrityAssociates, Inc.
| |
| Table 3: VY Thermal Transients (continued) ip flo ,JPiping 1 1 TFf) -
| |
| ~~~Th-eno
| |
| [
| |
| Condition, 14[1[7[1(8101 TImo R IO Flo- [ 91 WIWIo orN.
| |
| M.1n
| |
| ,F) ý T n-l n e o Rlgi.. Op r* N of Tempt. . I- *Ffh)
| |
| ' F (gpm) I (psig) (p"s* Cyd* 1lOI 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 15800 - 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 .
| |
| 23 225 530 225 5700 100 16.158 90 0 200 530 225 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 wn3 "6 225 330 225 37800 0 5.23 2 11 25 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 F100 5 225 100 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 0 450 100 0 lO0 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 R
| |
| 20 Wi tRaion R 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 1 225 225 225 0.01. 0 22,858 0 2 225 225 225 001 16,1 5 0 0
| |
| 3 225 225 225 0.01 16,:588 25 25 180 t800 60 22,858 25 25 225 2700 4 180 110 225 60 2700 9,143 25 25 5 .180 180 21 225 60 2700 4,572 25 25 150
| |
| (-) 1800 6 225 180 60 2700 4.572 25 25 225 225 60 6,700 "0 7A 0 0.01 0 IS5 150 0 6,700 0 225 225 225 0.01 0 237 25 9A 70 225 70 60 9300 6,700 25 25 9B 70 150 70 60 1290 File No.: VY-16Q-307 Page 11 of 16 Revision: 0 F0306-OI RO
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| | |
| StructuralIntegrity Associates, Inc.
| |
| Table 4: Recirc/RHR Piping Size Information [31 Regions 1,2 3 4 5 6 7A, 7B 8 9A, 9B I
| |
| 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 I
| |
| Pipe Weight' (lb/ft) 386.1 415.1 257.2 103.4 207.5 221.9 23.2 316.5 I
| |
| Note:
| |
| : 1. Weight of contents automatically added by the PIPESTRESS Program.
| |
| I 4.0 ANALYSIS I
| |
| 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 I
| |
| 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:
| |
| I h 0.023 Re0 8 Pr 0 4 k/D I
| |
| Where Re= Reynolds number Pr = Prandtl number k - Thermal conductivity I
| |
| D = Pipe diameter File No.: VY-16Q-307 Page 12 of 16 I
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| Revision: 0 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)° ýk/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) Region Pre-s-res (psig) 1,2, 7A 6, 7B Lad Set C-s I 2 3 3B 4 5 6 1 7A 7B . 8 9A 9B 9B I 3B I I 0 I4O I00 - o0o 100 00 100 1 100 00 100 100 I,100 1,100 120
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| .2 2 10 tO0 10 - 10 100 0 100 100 00 100 100 I004 50 50 50 3 3 549 549 549 - 549 549 " 549 549 150 549 549 150 120 1,010 1,035 4 4 542 542 542 542 542 542 542 " 50 542 542 150 1,010 1,035 120 5 5 526 526 526 226 5 526 526 526 150 526 526 150 1,010 1,035 : 20 6 6 542 542 542 - 542 542 542 542 150 542 542 150 1,010 1,035 120 7 7 526 526 526 - 526 526 526 526 150 526 526 150 1,010 1,035 120 8 8 516 516 516 - 516 516 516 516 150 516 516 :50 t,010 1,035 120 9 9 526 526 526 - 526 526 526 "526 150 . 526 526 150 1,010 1,035 120 10 10 300 300 305 300 300 300 300 150 300 300 150 1,135 1,160 120 II I11 55O 500 500 - 500 500 500 500 150 500 500 . 150 1,1355 1,160 120 12 12 300 300 300 - 300 305 300 300 150 300 300 150 675 700 121 13 13 549 549 549 -. 549 549 549 549 150 549 549 150 1010 1,035 120 14 14 549 549 549 - 549 549 549 549 150 549 . 549 ISO 1,010 1,035 120 Is 15 375 375 375 - 375 375 375 375 150 375 375 I50 170 195 120 16 16 530 330 350 3305 330 550 330 IS0 330 530 IS0 115 90 90 17 17 225 225 225 225 225 225. 225 ISO 225 225 IS0 0 25 0 is 18 100 100 loo 100 100 '10 100 100 100 100 IO 10 . 00 1563 25 0 25 19 19 100 100 100 - 0Go 100 100 0 0 100 100 " OS0 100 1,563 450 0
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| 20 20 225 225 225 225 225 225 225 225 225 225 225 225 25 0 25 45 21 21 225 225 225 ISO 4 10 190 1SO 225 150 225 70 70 25 0 25 File No.: VY-16Q-307 Page 13 of 16 Revision: 0 F0306-O1 RO
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| StructuralIntegrityAssociates, Inc.
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| 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.
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| 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.
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| results represent the full projected 60 year cycle count.).
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| 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.
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| Appendix A contains the PIPESTRESS input files. Appendix B contains the fatigue usage summary for both locations.
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| I I
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| I File No.: VY-16Q-307 Page 14 of 16 Revision: 0 F0306-01RO Ii
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| 1 StructuralIntegrity Associates, Inc.
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| I
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| | |
| ==6.0 REFERENCES==
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| : 1. ASME Boiler and Pressure Vessel Code, Section III, 1998 Edition with 2000 Addenda.
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| : 2. ASME Boiler and Pressure Vessel Code, Section XI, 1998 Edition.
| |
| : 3. Vermont Yankee Calculation 23A5569, "Recirculation System Stress Analysis Loop A",
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| 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.
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| 13 Holman, J.P., Heat Transfer, Fifth Edition, McGraw-Hill, 1981.
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| File No.: VY-16Q-307 Page 15 of 16 Revision: 0 F0306-OIRO
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| I VStructural IntegrityAssociates, Inc.
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| I
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| : 14. SI Calculation, "Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell/Bottom Head," Revision 0, SI File Number VY-16Q-303.
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| I
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| : 15. VY Drawings, SI File No. VY-16Q-205: I
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| : 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. I
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| : c. 5920-6808 Sheet 1, Revision 0.
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| I I
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| .File No.: VY-16Q-307 Revision: 0 Page 16 of 16 I F0306-OIRO I
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| v StructuralIntegrityAssociates, Inc.
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| APPENDIX A PIPESTRESS Input Files Input File Description Recirc_15.fre Piping model and general input
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| - for reduced cycle count RHR 15.fre. Piping model and general input
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| - 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 Page Al of A51 Revision: 0 F0306-01 RO
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| VStructuralIntegrityAssociates, Inc.
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| I I
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| Recirc 15.fre IDEN. JB=3 CD=l GR=-Y
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| *Job number (I to 9999)
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| *I=ASME Class 1
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| *Direction of gravity I
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| VA=O *0=Calculate 2=Verify IU=l OU=l CH=$
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| *Input units
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| *Output units
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| *Delimiter character 1=USA 1=USA I AB=T *FREE errors abort PL=$Vermont Yankee$
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| EN=$RVP$
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| TITL BL=3 *Modeling option:
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| I
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| * 3 = uniform mass for static analysis GL=1
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| *
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| *
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| * lumped mass for dynamic analysis rotational inertia
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| *Report forces/moment ignored 0=Global l=Local 2--G et L I
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| SU=l *Support summary 0=No l=Yes CV=I5 HS=l MD=l
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| *Code version - See Manual
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| *Highest 20 stress
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| *Hot modulus ratios, for each case I J6=l *File generated by program TI=$Vermont Yankee Recirculation $
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| $Fatigue Analysis$
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| FREQ RF=l RP=8 FR=36 MP=20 RC=0'MX=70 TI=$SEISMIC$
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| I THERMAL CYCLE LOAD CASES**** I LCAS RF=0 CA=1 TY=0 TI=$LC-l$ *TC-1 LCAS.
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| LCAS LCAS RF=0 RF=0 RF=0 CA=2 TY=0 CA=3 TY=0 CA=4 TY=0 TI=$LC-2$
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| TI=$LC-3$
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| TI=$LC-4$
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| *TC-2
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| *TC-3
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| *TC-4 I
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| LCAS RF=0 CA=5 TY=0 TI=$LC-5$ *TC-5 LCAS LCAS LCAS.
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| RF=0 RF=0 RF=0 CA=6 TY=0 CA=7 TY=0 CA=8 TY=0 TI=$LC-6$
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| TI=$LC-7$
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| TI=$LC78$
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| *TC-6
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| *TC-7
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| *TC-8 I
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| LCAS RF=0 CA=9 TY=0 TI=$LC-9$ *TC-9 LCAS LCAS LCAS
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| .RF=0 RF=0 RF=0 CA=I0 TY=0 CA=I1 TY=0 CA=12 TY=0 TI=$LC-10$
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| TI=$LC-11$
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| TI=$LC-12$
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| *TC-10
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| *TC-11
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| *TC-12 I
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| LCAS RF=0 CA=13 TY=0 TI=$LC-13$ *TC13 LCAS LCAS LCAS RF=0 RF=0 RF=0 CA=14 TY=0 CA=I5 TY=0 CA=16 TY=0 TI=$LC-14$
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| TI=$LC-15$
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| TI=$LC-16$
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| *TC-14
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| *TC-15
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| *TC-16 I
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| LCAS RF=0 .CA=17 TY=0 TI=$LC-17$ *TC-17 LCAS LCAS LCAS RF=0 RF=0 RF=0 CA=18 TY=0 CA=l 9 TY=0 CA=20 TY=0 TI=$LC-18$
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| TI=$LC-19$
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| TI=$LC-20$
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| *TC-18
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| *TC-19
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| *TC-20 I
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| LCAS RF=0 CA=21 TY=0 TI=$LC-21$ *TC-21 LCAS LCAS LCAS RF=0 RF=0 RF=0 CA=22 TY=O CA=23 TY=0 CA=24 TY=0 TI=$LC-22$
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| TI=$LC-23$
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| TI=$LC-24$
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| *TC-22
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| *TC-23
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| *TC-24 I
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| LCAS RF=0 CA=25 TY=0 TI=$LC-25$ *TC-25
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| **** WEIGHT CASES****
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| I LCAS CA=I01 LCAS CA=102 RF=l RF=2 TY=3 TY=4 TI=$OPERATING WEIGHT$
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| TI=$HYDROTEST WEIGHT$ I File No.: VY-16Q-307 Revision: 0 Page A2 of A51 I
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| F0306-OIRO I
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| V StructuralIntegrity Associates, Inc.
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| ******* ************* *********
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| **** THERMAL TRANSIENT CASES****
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| ** *** * * ** *** ** * *** ** ** ** * ** *** **
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| TCAS CA=201 TI=$Design Hydrotest (+ ))
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| TCAS CA=202 TI=$Design Hydrotest (-
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| TCAS CA=203 TI=$Startup TCAS CA=204 TI=$TRoll & Inc. PWR1 TCAS CA=205 TI=$TRoll & Inc. PWR2 TCAS CA=206 TI=$LOFWH+TT PWRI TCAS CA=207 TI=$LOFWH+TT PWR2 TCAS CA=208 TI=$LOFWH+PFWHTR Bypl TCAS CA=2 09 TI=$LOFWH+PFWHTR Byp2 TCAS CA=210 TI=$LOFWP, ISO Cl DN 1 TCAS CA=211 TI=$LOFWP, ISO Cl UP 1 TCAS CA=212 TI=$LOFWP, ISO Cl DN 2 TCAS CA=213 TI=$LOFWP, ISO Cl UP 2 TCAS CA=214 TI=$Reduction to 0% PWR TCAS CA=215 TI=$Shutdownl TCAS CA=216 TI=$Shutdown2 TCAS CA=217 .TI=$Shutdown3 TCAS CA=218 TI=$Shutdown4 TCAS CA=219 TI=$Code Hydrotest TCAS CA=220 TI=$RHR Initiation UP TCAS CA=221 TI=$RHR Initiation DN TCAS CA=222 TI=$Inadvert. Inj.. DOWN TCAS CA=223 TI=$Inadvert. Inj. UP TCAS CA=224 TI=$Sihgle Relief BD DN TCAS CA=225 TI=$Single Relief BD UP
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| ** SEISMIC CASES****
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| RCAS CA=103 EQ=3 EV=l TY=l SU=l LO=l FX=l FY=l FZ=l TI=$OBE INERTIA$
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| **** LOAD COMBINATION CASES
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| * CCAS RF=I CA=104 ME=l FL=l C1=103 CY=10 TI=$OBE$
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| CCAS RF=l CA=401 SS=l ME=I EQ=3 C1=10.l C2=103 TI=$EQUATION .9 LEVEL B$
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| CCAS RF=I CA=402 SS=1 ME=3 Fl=l C1=103 C2=1 TI=$NORMAL+OBE$
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| CCAS RF=l CA=403 SS=l ME=3 Fl=-l C1=103 C2=1 TI=$NORMAL-OBE$
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| **** LOAD SETS****
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| * ** * ** **** ******
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| LSET RF=I FC=0 RP=1 CY=60 PR=1 MO=l TR=201 TI=$Design Hydrotest (+)LS-I$
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| LSET RF=2 FC=0 RP=1 CY=60 PR=2 MO=2 TR=-202 TI=$Design Hydrotest (-)LS-2$
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| LSET RF=3 FC=0 RP=1 CY=150 PR=3 MO=3 TR=203 TI=$Startup LS-3$
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| .LSET RF=3 FC=0 RP=1 CY=290 PR=4 MO=4 TR=-204 TI=$TRoll & Inc. PWRI LS-4$
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| LSET RF=4 FC=0 RP=1 CY=290 PR=5 MO=5 TR=-205 TI=$TRoll & Inc. PWR2 LS-5$
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| LSET RF=4 FC=0 RP=I CY=I0 PR= 6 .MO=6 TR=206 TI=$LOFWH+TT PWRI LS-6$
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| LSET RF=4 FC=0 RP=1 CY=I0 PR=7 MO=7 TR=-207 TI=$LOFWH+TT PWR2 LS-7$
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| LSET RF=5 FC=0 RP=l CY=35 PR=8 MO=8 TR=-208 TI=$LOFWH+PFWHTR Bypl LS-8$
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| LSET RF=5 FC=0 RP=l CY=35 PR=9 MO=9 TR=209 TI=$LOFWH+PFWHTR Byp2 LS-9$
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| LSET RF=5 FC=0 RP=l CY=5 PR=I0 MO=I0 TR=-210 TI=$LOFWP, ISO Cl DN 1 LS-10$
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| LSET RF=I1 FC=0 RP=l CY=I0 PR=lI MO=ll TR=211 TI=$LOFWP, ISO Cl UP 1 LS-II$
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| LSET RF=I1 FC=0 RP=I CY=10 PR=I2 MO=12 TR=-212 TI=$LOFWP, ISO Cl DN 2 LS-125 LSET RF=3 FC=0 RP=l CY=5 PR=13 MO=13 TR=213 TI=$LOFWP, ISO Cl UP 2. LS-13$
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| LSET RF=3 FC=0 RP=l CY=150 PR=14 MO=14 TR=214 TI=$Reduction to 0% PWR LS-14$
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| File No.: VY-16Q-307 Page A3 of A51 Revision: 0 F0306-OIRO
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| I CStructuralIntegrityAssociates, Inc.
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| I LSET LSET LSET RF=5 RF=15 RF=I16 FC=0 FC=0 FC=0 RP=I RP=I RP=I CY=150 CY=150 CY=150 PR=15 PR=16 PR=17 MO=15 MO=16 MO=17 TR=-215 TR=-216 TR=-217 TI=$Shutdownl TI=$Shutdown2 TI=$Shutdown3 LS-15$
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| LS-16$
| |
| LS-17$
| |
| I LSET RF=2 0 FC=0 RP=1 CY=150 PR=18 MO=18 TR=-218 TI=$Shutdown4 LS-18$
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| LSET LSET LSET RF=1 9 RF=20 RF=20 FC=0 FC=0 FC=0 RP=1 RP=I RP=I CY=1 CY=150 CY=150 PR=19 PR=20 PR=21 MO=19 MO=20 MO=21 TR=219 TR=220 TR=-221 TI=$Code Hydrotest TI=$RHR Initiation TI=$RHR Initiation UP DN LS-19$
| |
| LS-20$
| |
| LS-21$
| |
| I LSET RF=5 FC=0 RP=1 CY=0 PR=22 MO=22 TR=-222 TI=$Inadvert. Inj. DOWN LS-22$
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| LSET LSET LSET RF=5 RF=23 RF=24 FC=0 FC=0 FC=0 RP=I RP=1 RP=I CY=0 CY=0 CY=o PR=23 PR=24 PR=25 MO=2 3 MO=2 4 MO=2 5 TR=223 TR=-224 TR=225 TI=$.Inadvert. Inj. UP TI=$Single Relief BD DN TI=$Single Relief BD UP LS-23$
| |
| LS-24$
| |
| LS-25$
| |
| I LSET RF=2 FC=O CY=5 FL=I LSET RF=2 FC=0 CY=5 FL=I PR=2 MO=402 TI=$NORMAL+OBE PR=2 MO=403 TI=$NORMAL-OBE LS-26$
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| LS-27$ I
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| *FATG AT=500 AF=502
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| *FATG AT=600 AF=602 I
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| U
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| **** 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 3.30/0.700 0.40/0.100 4.40/0.750 0.90/0.20 0 4.41/0.90 0 1.25/0.400 4.75/1.100 2.25/0.450 5.20/1.100 8.70/1.600 12.00/0.650 17.00/0.40 0 20.00/0.350 30.00/0.350 36.00/0.350 2.30/0.700 5.80/1.600 I DI=Y 0.30/0.030 2.00/0.220 8.25/0.330 0.40/0.030 2.40/0.350 0.50/0.05' 0 3.50/0.35' 0 0.60/0.075 3.60/0.300 1.00/0.075 1.20/0.100 5.30/0.300 5.75/0.330 8.75/0.250 17.50/0.25' 0 25.00/0.120 30.00/0.120 36.00/0.120 I
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| DI=Z 0.30/0.100 1.90/0.600 0.40/0.100 3.50/0.600 0.50/0.13' 0 3.75/0.70' 0 0.90/0.150 4.40/0.700 8.50/1.500 12.50/0.500 20.00/0.35' 0 30.00/0.350 36.00/0.350 1.00/0.250 1.60/0.250 4.50/0.800 6.25/1.500 I
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| **** MATERIAL PROPERTIES ***
| |
| I
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| * ASTM A*-106 C rade B, PIPE MATH CD=106 MATD TE=70 EX=0 EH=29.5
| |
| * TY=1 EX=0. 0
| |
| *C-Si SM=20.0 SY=35 SY=35 I
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| MATD TE=100 EH=29.3 EX=0.20 SM=2 0. 0 U
| |
| MATD TE=200 EH=28.8 E.X=l. 00 SM=20.0 SY=32. 1 MATD TE=300 EH=28.3 E:X=l. 90 SM=2 0.0 SY=31 MATD TE=400 EH=27.7 E:X=2.80 SM=20. 0 SY=29. 9 MATD TE=500 EH=27.3 E X=3.70 SM=18. 9 SY=28.5 MATD TE=600 EH=26.7
| |
| * ASME SA-376 Grade TP316, MATH CD=376.31 6 EX=0 E X=4.70 P IPE
| |
| * T Y=4 SM=17 .3 SY=26. 8
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| *16Cr-12Ni-2Mo I
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| MATD TE=70 EH=28.3 .E X=0.0 SM=20.0 SY=30.0 MATD TE=100 EH=28.1 E:X=0.30 SM=20.0 SY=30.0 MATD TE=200 MATD TE=300 MATD TE=400 EH=27.6 EH=27.0 EH=26.5 E:X=1.40 E X=2. 50 E X=3.70 SM=20.0 SM=20.0 SM=19.3 SY=25.9 SY=23.4 SY=21.4 I
| |
| MATD TE=500 MATD TE=600 EH=25.8 EH=25.3
| |
| * ASME SA-403 Grade WP316, E) <=5. 00 E}K=6.30 ElLBOWS
| |
| * SM=18.0 SM=17.0 SY=20.0 SY=18.9 I MATH CD=403.316 EX=0 TE(=4 *16Cr-12Ni-2Mo E>ý=0. 0 MATD TE=70 File No.: VY-16Q-307 EH=28.3 SM=20.0 SY=30.0 Page A4 of A51 I
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| Revision: 0 F0306-01 RO I
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| S structuralInterityAssociates, Inc.
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| MATD TE=l( EH=28 .1 EX=0. 30 SM=20.0 SY=30.0 MATD TE-=2( EH=27. 6 EX=I. 40 SM=20.0 SY=25. 9 MATD TE=3( EH=27 .0 EX=2. 50 SM=20. 0 SY=23. 4 MATD TE=4( EH=26. 5 EX=3.70 SM=18.7 SY=21.4 MATD TE=5( EH=25.8 EX=S.00 SM=17.5 SY=2 0.0 MATD TE=6( EH=2 5.3 EX=6. 30 SM=16.4 SY=18. 9
| |
| *** Cross Sectional Properties CROS CD=l OD=50.0 WT=8.87 MA=3977.2 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=1 ST=l. 0 *RECIRCULATION OUTLET NOZZLE CROS CD=2 OD=37.85 WT=6. 1 MA=2122.2 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=1 ST=I. 0 CROS CD=3 OD=28.875 WT=l.56 MA=4 84.9 *CALC. PER GE SPEC. NO. 23A5569 [.3]
| |
| SO=1 ST=I. 0 CROS CD=4 OD=28. 638 WT=l.45 MA=450. 4 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=1 ST=l. 0 CROS CD=5 OD=28.169 WT=l.244 MA=386. 1 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=1 ST=1. 0 CROS CD=7 OD=28. 166 WT=2.125 MA=0. 001 *VALVE SO=1 ST=l. 0 KL= -1 CROS CD=8 OD=42. 507 WT=2.486 MA=0.001 *PUMP SO=. 001 ST=. 001 KL=1 CROS CD=ll OD=6. 625 WT=0.432 MA=0. 001 *PUMP RIGID STRUTS SO=0. 001 ST=0. 001 KL=l CROS CD=13 OD=28.339 WT=l. 339 MA=415. 1 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| S0=I ST=l CROS CD=14 OD=28.339 WT=2. 67 MA=0. 001 *VALVE SO=1 ST=1 .0 KL=1 CROS CD=15 OD=12.748 WT=0. 685 MA=103.4 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=1 ST=l. 0 CR0S CD=16 OD=14.17 WT=1. 395 MA=207 .5 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| S0=1 ST=l. 0 CROS CD=17 OD=15.5 WT=2 MA=307 .7 *CALC.. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=I ST=l .0 CROS CD=18 OD=21. 88 WT=4.06 MA=803.2
| |
| * CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=1 ST=l.0 CROS CD=19 OD=28.25 WT=7.25 MA=1673.1 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=1 ST=I. 0 CROS CD=20 OD=21. 878 WT=l. 043 MA=257.2 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=1 ST=l. 0 CROS CD=25 OD=20 WT=l.031 MA=221. 9 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=1 ST=1 CROS CD=26 OD=20 WT=1. 875 MA=0. 001 *VALVE SO=1 ST=1 KL=I CROS CD=27 OD=4 .5 WT=0. 3385 MA=23.2 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=l1 ST=1 KL:I *4 inch bypass line CROS CD=28 oD=4. 5 WT=0. 67 MA=0. 001 *VALVE V2-54A SO=I ST=I KL=1 CRoS CD=29 OD=24 WT=1.217 MA=316. 5 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=1 SrT=1 CROS CD=30 OD=2 4 WT=2.43 MA=0. 001 *VALVE SO=1 ST=1 KL=1 CROS CD=40 OD=4. 5 WT=0.3385 MA=0. 001 *4 inch bypass STRUTS SO=0.001 ST=0. 001 KL=l CROS CD=41 OD=2.875 WT=0. 276 MA=0. 001 *STRUT RDAI, RDA5, & VBAI SO=0.001 ST=0.001 KL=l CROS CD=42 OD=28.339 WT=l. 339 MA=0. 001 *RIGID FROM RECIRC ELBOW TO RDAl STRUT SO=0.001 ST=0.001 KL=I
| |
| * STRUCTURE AND LOADS
| |
| ******** **************
| |
| File No.: VY-16Q-307 Page A5 of A51 Revision: 0 F0306-01 RO
| |
| | |
| I V StructuralIntegrityAssociates, Inc.
| |
| I
| |
| * ------------------------
| |
| DESN TE=575.0
| |
| *--7----------------------------
| |
| PR=1250.0 *Reference 12 GE Design Requirements 7----------------------------------
| |
| -----------------------------
| |
| Rpt VY-05Q-227 I
| |
| ------ *-------------------------------------------
| |
| *BEGIN REGION 1 TRANSIENT CARDS & GEOMETRY FROM RHR SUPPLY TO TEE
| |
| --------------------------------------------------- I INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG1.INP.
| |
| *RUN
| |
| *GROUP 1 FROM ANCHOR TO REACTOR VESSEL N3B 1 FROM ANCHOR TO REACTOR VESSEL N3B I
| |
| *NOTE
| |
| *NOTE
| |
| *NOTE
| |
| *NOTE NODE 003 - RECIRC SUCTION NOZZLE NIA (EL. 279'5 INCH)
| |
| NODE 003 IS AT THE SAFE END TO VESSEL NOZZLE CONNECTION I
| |
| *NOTE SAFE END FROM NODES 003 TO 808
| |
| *NOTE
| |
| *NOTE
| |
| *NOTE CONNECTION TO VESSEL AT NODE 003 OD AND WALL THICKNESS FOR SAFE END TAKEN FROM GE CALC WEIGHT FOR SAFE END BASED ON THICKNESS I
| |
| *NOTE MATL CROS COOR CD=376.316 CD=1 PT=3 AX=0 AY=0 AZ=0 I
| |
| ANCH AMVT AMVT AMVT PT=3 CA=I CA=2 CA=3 PT=3 PT=3 PT=3 DX=0. 0000 DX=0. 0000 DX=0. 0000 DY=0. 0176 DY=0. 3141 DY=0.3112 DZ=-0.0201 DZ=O. 3602 DZ=-0. 3568 I
| |
| AMVT AMVT AMVT CA=4 CA=5 CA=6 PT=3 PT=3 PT=3 DX=0.0000 DX=0.0000 DX=0. 0000 DX=0. 0000 DY=0. 2995 DY=0. 3112 DY=0.2 995 DZ=-0. 3434
| |
| *DZ=-0.3568 DZ=-0. 3434 DZ=-0. 3350 I
| |
| AMVT CA=7 PT=3 DY=0. 2922 AMVT AMVT AMVT AMVT CA=8 CA=9 CA=10 CA=11 PT=3 PT=3 PT=3 PT=3 DX=0. 0000 DX=0.0000 DX=0.0000 DX=0. 0000 DY=0.2 995 DY=0. 1422 DY=0.2807 DY=0. 1422 DZ=-0. 3434 DZ=-0. 1630 DZ=-0* 3218 DZ=-0. 1630 I
| |
| AMVT AMVT AMVT AMVT CA=12 CA=I3 CA=14 CA=15 PT=3 PT=3 PT=3 PT=3 DX=0.0000 DX=0.0000 DX=0. 0000 DX=0. 0000 DY=0. 3141 DY=0. 3141 DY=0. 1928 DY=0. 1624 DZ=-0.3602 DZ=-0. 3602 DZ=-0.2521 DZ=-0. 1986 I
| |
| AMVT AMVT AMVT CA=16 CA=17 CA=18 PT=3 PT=3 PT=3 DX=0.0000 DX=0. 0000 DX=0. 0000 DY=0.0946 DY=0.0176 DY=0. 0176 DZ=-0. 1084 DZ=-0. 0201 DZ=-0. 0201 I
| |
| AMVT CA=19 PT=3 DX=0.0000 DY=0. 0946 DZ=-0..1084 AMVT AMVT AMVT CA=20 CA=21 CA=22 PT=3 PT=3 PT=3 DX=0.0000 DX=0. 0000 DX=0. 0000 DY=0. 0946 DY=0. 0361 DY=0. 2995 DZ=70.1084 DZ=-0. 0413 DZ=-0. 3434 I
| |
| AMVT CA=23 PT=3 DX=O 0000 DY=0. 1928 DZ=-0.2521 AMVT CA=24 PT=3 DX=0. 0000 DY=0. 0176 DZ=-0. 0201 I
| |
| TANG CROS TANG PT=805 CD=2 PT=806 DZ=-1.017 DZ=-0.823 EW=1 EW=1 I
| |
| CROS CD=3 TANG CROS TANG PT=807 CD=4 PT=808 DZ=-0.58 DZ=-0.47 EW=1 I
| |
| CROS CD=5 TANG PT=5 DZ=-5.59 EW=1 FileNo.: VY-16Q-307 Revision: 0 Page A6 of A51 I F0306-OI RO I
| |
| | |
| U StructuralIntegrityAssociates, 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 FNýZ:\SISJ-PROJECTS\VY-16Q\RevO\REG2.INP TANG PTýII DY=-2.22 EW=I CROS CD=5 TANG PT=12 DY=-I.78 TANG PT-20 DY=-6.77 TANG PT=22 DY=-3.25 TANG PT=25 DY=-15.49 EW=1 MATL CD=403.316 BRAD PT=26 RA=3.5 EW=1 MATL CD=376.316 TANG PTh27 DX=-3.3 DZ=I.27 EW=1 CROS CD=7 VALV PTh30 DX=-2.28 DZ=0.89 MA=l0.368 PL=l 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=I.132 JUNC PT=40 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=I.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=O LUMP PT=50 MA=28. *NOTE WEIGHT OF PUMP FLOODIED 28K (EXCLUDIN G 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
| |
| *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 Page A7 of A51 Revision: .0 F0306-OI RO
| |
| | |
| StructuralIntegrityAssociates, Inc. "
| |
| I JUNC CROS PT=50 CD=8 I
| |
| RIGD PT=54 DX=l.06 DZ=I.06 RIGD JUNC RIGD PT=56 DX=l.06 DY=0.75 DZ=I.06 PT=50 PT=66 DZ=-3.83
| |
| *NOTE CONSTANT SUPPORT HA3 AT NODE 56 U
| |
| RIGD PT=69 DY=l *NOTE CONSTANT SUPPORT HA4 AT NODE 69 JUNC CROS RIGD PT=50 CD=8 PT=60.DX=-3.83 I
| |
| RIGD PT=63 DY=1 *CONSTANT SUPPORT HAS AT NODE 63
| |
| *
| |
| *
| |
| * CODING.FOR PUMP RIGID STRUTS CODED FROM PUMP CENTERLINE FOLLOW *** I CROS CD=1I JUNC PT=66 RIGD PT=15 DY=0.7071 DZ=-0.7071 I JUNC PT=60 RIGD PT=16 DX=-0.7071 DY=0.7071
| |
| * *** END OF CODING FOR PUMP SUPPORTS ***
| |
| *PUMP INLET I
| |
| CROS CD=8 JUNC PT=50 TANG PT=150 DX=-2.17 BRAN PT=151 DZ=2 333 TE=I 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 I
| |
| CROS CD=14 VALV PT=160 PL=I DX=0.0 DY=0.0 JUNC PT=160 DZ=2.52 MA=6.8285 I
| |
| 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 I
| |
| CROS CD=13 MATL CD=403.316 BRAD PT=175 RA=3.5 MATL CD=376.316 EW=l I 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***
| |
| I TANG PT=184 DY=4.42 TANG TANG TANG PT=186 PT=I88 PT=189 DY=3.02 DY=1.51 DY=0.74 I
| |
| TANG PT=190 DY=I.15 EW=I TANG PT=600 DY=I.06
| |
| ***INPUT FILE TO INCLUDE EFFECTS OF RHR INITIATION ON LINE NEAR RHR RETURN TO HEADER I
| |
| INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG3B.INP JUNC TANG PT=600 PT=I95 DY=2.08 EW=I 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 Revision: 0 Page A8 of A51 I F0306-OI RO I
| |
| | |
| Structural IntegrityAssociates, 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 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=1 *AL=$CONC. REDUCERS CROS CD=15 TANG PT=330 DY=4.58 TANG PT=335 DY=3.29 EW=1 MATL CD=403.316 BRAD PT=334 RA=1.5 EW=1
| |
| * --------------------
| |
| *END REGION 5 GEOMETRY RISER TO NOZZLE NODE 336
| |
| ---------------------
| |
| * ------------------------------
| |
| *BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO NOZZLE NODE 336
| |
| -------------------------------
| |
| -*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=1 CROS CD=17 TANG PT=836 DX:0.37 EW=1 CROS CD=18 TANG PT=835 DX=0.53 EW=1 CROS CD=19 TANG PT=336 DX=0.704 EW=1 NOZZ PT=336 AMVT CA=1 PT=336 DX=-0. 0201 DY=0.0246 DZ=0.0000 AMVT CA=2 PT=336 DX=-0.3602 DY=0. 4398 DZ=0.0000 AMVT CA=3 PT=336 DX=-0. 3568 DY=0. 4316 DZ=0.0000 AMVT CA=4 PT=336 DX=-0. 3434 DY=0. 4152 DZ=0.0000 AMVT CA=5 PT=336 DX=-0. 3568 DY=0.4050 DZ=0. 0000 AMVT CA=6 PT=336 DX=-0 3434 DY=0.2940 DZ=0.0000 AMVT CA=7 PT=336 DX=-0.3350 DY=O0.3229 DZ=0. 0000 AMVT CA=8 PT=336 DX=-0. 3434 DY=0. 2700 DZ=0. 0000 AMVT CA= 9 PT=336 DX=-0. 1630 DY=0.1991 DZ=0. 0000 AMVT CA=10 PT=336 DX=-0. 3218 DY=0. 1626 DZ=0 .0000 AMVT CA=11 PT=336 DX=-0. 1630 DY=0. 0246 DZ=0. 0000 AMVT CA=12 PT=336 DX=-0.3602 DY=0.4398 DZ=0. 0000 AMVT CA=13 PT=336 DX=-0. 3602 DY=0. 4316 DZ=0. 0000 AMVT CA=14 PT*=336 DX=-0 .2193 DY=0. 4152 DZ=0. 0000 AMVT CA=15 PT=336 DX=-0. 1862 DY=0.4050 DZ=0. 0000 AMVT CA=f 6 PT=336 DX=-0. 1084 DY=0. 2940 DZ=0. 0000 AMVT CA=17 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=1 9 PT=336 DX=-0. 1084 DY=~0.1991 DZ=~0.0000 File No.: VY-16Q-307 Page A9 of A51 Revision: 0 F0306-0I RO
| |
| | |
| StructuralIntegrityAssociates, 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,[
| |
| *-------------------------- ------------
| |
| *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
| |
| ---------- -----------
| |
| -------------------------------
| |
| *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 Revision:. 0 Page A10 of A51 I F0306-0 IRO I
| |
| | |
| V StructuralIntegrityAssociates, Inc.
| |
| MATL CD=376. 316 TANG PT=868 DX=1.8 DZ=-3.1 CROS CD=16 TANG PT=867 DX=0.4375 DZ=-0.76 EW=1 CROS CD=17 TANG PT=866 DX=0.185 DZ=-0.32 EW=1 CROS CD=18 TANG PT=865 D. X=0.265 DZ=-0.46 EW=1 CROS CD=19 TANG PT=366 D:X=0.352 .DZ=-0.61 EW=1 NOZZ PT=366 AMVT CA=1 PT=366 DX=-0.0101 DY=0.0246 DZ=0.0174 AMVT CA=2 PT=366 DX=-0.180.0 DY=0. 4398 DZ=0: 3120 AMVT CA=3 PT=366 DX=-0. 1783 DY=0. 4357 DZ=0. 3091 AMVT CA=4 PT=366 DX=-0. 1716 DY=0. 4193 DZ=0.2974 AMVT CA=5 PT=366 DX=-0. 1783 DY=0. 4357 DZ=0. 3091 AMVT CA=6 PT=366 DX=-0. 1716 DY=0. 4193 DZ=0.2974 AMVT CA=7 PT=366 DX=-0. 1674 DY=0. 4091 DZ=0.2902 AMVT CA= 8 PT= 3 66, DX=-0. 1716 DY=0 4193 DZ=0.2974 AMVT CA=9 PT=366 DX=-0. 0815 DY=0. 1991 DZ=0. 1412 AMVT CA=10 PT=366 DX=-0. 1609 DY=0.3930 DZ=0. 2788 AMVT CA=11 PT=366 DX=-0. 0815 DY=0. 1991 DZ=0. 1412 AMVT CA=12 PT=366 DX=-0. 1800 DY=0. 4398 DZ=0. 3120 AMVT CA=13 PT=366 DX=-0. 1800 DY=0. 4398 DZ=0. 3120 AMVT CA=14 PT=366 DX=-0. 1097 DY=0. 2678 DZ=0. 1899 AMVT CA=15 PT=366 DX=-0. 0931 DY=0. 2275 DZ=0. 1613 AMVT CA=16 PT=366 DX=-0. 0542 DY=0. 1324 DZ=0.0939 AMVT CA=17 PT=366 DX=-0. 0101 DY=0. 0246 DZ=0 .0174 AMVT CA=18 PT=366 DX=-0. 0101 DY=0. 0246 DZ=0. 0174 AMVT CA=19 PT=366 DX=-0. 0542 DY=0. 1324 DZ=0. 0939 AMVT CA=20 PT=366 DX=-0. 0101 DY=0. 02.46 DZ=0 .0174 AMVT CA=21 PT=366 DX=-0. 0207 DY=0.0505 DZ=0. 0358 AMVT CA=22 PT=366 DX=-0. 1716 DY=0. 4193 DZ=0.2974 AMVT CA=23 PT=366 DX=-0. 1105 DY=0.2700 DZ=0. 1915 AMVT CA=24 PT=366 DX=-0 0101 DY=0.0246 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 Page All of A51 Revision: 0 F0306-O1 RO
| |
| | |
| I V StructuralIntegrity Associates, Inc.
| |
| I
| |
| *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 I
| |
| CRED PT=317 DX=0.75 DZ=-1.3 AN=30 CROS TANG BRAD CD=15 PT=313 DX=0.5525 DZ=-0.957 PT,=400 RA=1.5 EW=1 EW=1 I TANG PT=310 DX=3.483 DZ=-2.011 EW=1 MATL BRAD MATL CD=403.316 PT=311 RA=1.5 EW=I CD=376.316 U
| |
| CR0S CD=15 TANG TANG MATL PT=312 DY=4.74 PT=314 DY=6.99 CD=403.316 EW=I I BRAD PT=315 RA=1.5 EW=1
| |
| ----------------------
| |
| *END REGION
| |
| ---------------------
| |
| 5 GEOMETRY RISER TO NOZZLE NODE 316 I
| |
| -------------------------------
| |
| *BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO NOZZLE NODE 316
| |
| * ---------------------
| |
| U
| |
| *GROUP 6 TO NOZZLE NODE 316 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP MATL CD=376.316 I
| |
| TANG PT=818 DX=1.84 DZ=3.19 CROS TANG CROS CD=16 PT=817 DX=0.4375 DZ=0.76 CD=17 EW=1 I TANG PT=816 DX=0.185 DZ=0.32 EW=1 CROS TANG CROS CD=18 PT=815 DX=0.265 DZ=0.46
| |
| .CD=19 EW=1 I TANG PT=316 DX=0.352 DZ=0.61 EW=I NOZZ AMVT AMVT PT=316 CA=I CA=2 PT=316 PT=316 DX=-0. 0101 DX=-O. 1800 DY=0. 0246 DY=0. 4398 DZ=-O. 0174 DZ=-0.3120 I
| |
| AMVT CA=3 PT=316 DX=-0. 1783 DY=0.4 357 DZ=-0. 3091 AMVT AMVT AMVT CA=4 CA=5 CA=6 PT=316 PT=316 PT=316 DX=-O. 1716 DX=-0. 1783 DX=-O. 1716 DY=0. 4193 DY=0..4 357 DY=0. 4193 DZ=-0. 2974 DZ=-0. 3091 DZ=-0 .2974 I
| |
| AMVT CA=7 PT=316 DX=-O. 1674 DY=0. 4091 DZ=-0.2902 AMVT AMVT AMVT CA=8 CA=9 CA=-I 0 PT=316 PT=316 PT=316 DX=-O. 1716 DX=-O. 08 15 DX=-0. 1609 DY=0. 4193 DY=0. 1991 DY=0. 3930 DZ=-0 .2974 DZ=-0. 1412 DZ=-0.2788 I
| |
| AMVT CA=11 PT=316 DX=-0. 0815 DY=0. 1991 DZ=-0. 1412 AMVT AMVT AMVT CA=12 CA=13 CA= 14 PT=316 PT=316 PT=316 DX=-0. 1800 DX=-0. 1800 DX=-0. 1097 DY=0. 4398 DY=0.4398 DY=0 2678 DZ=-0. 3120 DZ=-0.3120 DZ=-0. 1899 U
| |
| AMVT CA=15 PT=316 DX=-0. 0931 DY=0. 2275 DZ=-0. 1613 AMVT AMVT AMVT CA=1 6 CA=I7 CA 18 PT=316 PT=316 PT=316 DX=-0. 0542 DX=-0. 0101 DX=-0. 0101 DY=0. 1324 DY=0. 0246 DY=0. 0246 DZ=-0.0939 DZ=-0.0174 DZ=-0. 0174 I
| |
| AMVT PT=316 DX=-0.0542 DY=0. 1324 DZ=-0.0939 I
| |
| CA=19 AMVT CA 20 PT=316 DX=-0.0101 DY=0. 0246 DZ=-0. 0174 AMVT CA=21 PT=316 DX=-0. 0207 DY=0. 0505 DZ=-0. 0358 AMVT CA=22 PT=316 DX=-0. 1716 DY=0. 4193 DZ=-0 .2974 File No.: VY-16Q-307 Revision: 0 Page A12 of.A51 I F0306-O1 RO I
| |
| | |
| IStructural IntegrityAssociates, 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 NOZZLE NODE 346
| |
| ----------------------------
| |
| 7
| |
| *GROUP 6 TO NOZZLE NODE 346 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP MATL CD=376.316 TANG PT=848 DX=3.17 DZ=-1.83 CROS CD=16 TANG PT=847 DX=0.758 DZ=-0.4375 EW=1 CROS CD=17 TANG PT=846 DX=0.32 DZ=-0..185 EW=1 CROS CD=18 TANG PT=845 DX=0.46 DZ=-0.265 EW=1 CROS CD=19 TANG PT=346 DX=0.61 DZ=-0.352 EW=1 NOZZ PT =346 AMVT CA=1 PT=346 DX=-0. 0174 DY=0. 0246 DZ=0. 0101 AMVT CA=2 PT=346 DX=-O. 3120 DY=0. 4398 DZ=0. 1800 AMVT CA=3 PT=346 DX=-O. 3091 DY=0. 4357 DZ=0. 1783 AMVT CA= 4 PT=346 DX=-0.2974 DY=0. 4193 DZ=0. 1716 AMVT CA=5 PT=346 DX=-0. 3091 DY=0. 4357 DZ=0. 1783 AMVT CA=6 PT=346 DX:-0.2974 DY=0. 4193 DZ=0. 1716 AMVT CA=7 PT=346 DX=-O. 2902 DY=0. 4091 DZ=0 1674 AMVT CA= 8 PT=346 DX=-O.2974 DY=0. 4193 DZ=0.1716 AMVT CA=19 PT=346 DX=-0. 1412 DY=0. 1991 DZ=0. 0815 AMVT CA=10 PT=346 DX=-0. 2788 DY=0 3930 DZ=0. 1609 AMVT CA=1I PT=346 DX=-0.1412 DY=0. 1991 DZ=0.0815 AMVT CA-12 PT=346 DX=-0 .3120 DY=0. 4398 DZ=0. 1800 AMVT CA=13 PT=346 DX=-0. 3120 DY=0. 4398 DZ=0. 1800 AMVT CA-14 PT=346 DX=-0. 1899 DY=0.2678 DZ=0.1097 AMVT CA=15 PT=346 DX=-0.1613 DY=0. 2275 DZ=0.0931 AMVT CA=' 6 PT=346 DX=-0. 0939 DY=0. 1324 DZ=0. 0542 AMVT CA=17 PT=346 DX=-0. 0174 DY=0.0246 DZ=0.0101 AMVT CA=18 PT=346 DX=-0. 0174 DY=0. 0246 DZ=0.0101 AMVT CA=19 PT=346 DX=-0. 0939 DY=0. 1324 DZ=0. 0542 AMVT CA=20 PT=346 DX=-0. 0174 DY=0.0246 DZ=0.0101 AMVT CA=21 PT=346 DX=-0. 0358 DY=0.0505 DZ=0.0207 File No.: VY-16Q-307 Page A13 of A51 Revision: 0 F0306-O1 RO
| |
| | |
| I V StructuralIntegrityAssociates, Inc.
| |
| I AMVT CA=22 PT=346 DX=-0.2974 DY=0.4193 DZ=0.1716 AMVT AMVT CA=23 CA=24 PT=346 PT=346 DX=-0.1915 DX=-0.0174 DY=0.2700 DY=0.0246 DZ=0.1105 DZ=0.0101 I
| |
| *END REGION 6 GEOMETRY TO NOZZLE NODE 346
| |
| ---------------------
| |
| ------------------------------
| |
| I
| |
| *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 I
| |
| JUNC PT=320 CROS CD=15 BRAN PT=322 DY=1.42 TE=2 I
| |
| TANG PT=324 DY=10.33 EW=1 MATL CD=403.316 BRAD PT=325 RA=1.5
| |
| *--------------------------
| |
| EW=1 I
| |
| *END REGION 5 GEOMETRY RISER TO NOZZLE NODE 326
| |
| ---------------------
| |
| *----------------------------
| |
| I
| |
| *BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO NOZZLE NODE 326
| |
| * ------------------------------
| |
| *GROUP 6 TO NOZZLE NODE 326 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP I
| |
| MATL TANG CROS CD=376. 316 PT=828 DX=3.18 DZ=1.84 CD=16 I
| |
| TANG PT=827 DX=0.758 DZ=0.4375 EW=1 CROS TANG CROS CD=17 PT=826 DX=0.32 DZ=0.185 CD=18 EW=1 I TANG PT=825 DX=0.46 DZ=0.265 EW=1 CROS TANG NOZZ CD=19 PT=326 DX=0.61 DZ=0.352 PT=326 EW=1 I AMVT CA=1 PT=326 DX=-0.0174 DY=0. 0246 DZ=-0.0101 AMVT AMVT AMVT CA=2 CA=3 CA=4 PT=326 PT=326 PT=326 DX=-0.3120 DX=-0. 3091 DX=-0.2974 DY=0. 4398 DY=0.4357 DY=0.4193 DZ=-0. 1800 DZ=-0. 1783 DZ=-O. 1716 I
| |
| AMVT CA=5 PT=326 DX=-0. 3091 DY=0.4357 DZ=-0. 1783 AMVT AMVT AMVT
| |
| .CA=6 CA=7 CA=8 PT=326 PT=326 PT=326 DX=-0.2974 DX=-0.2902 DX=-0.2974 DY=0.4193 DY=0. 4091 DY=0. 4193 DZ=-0.1716 DZ=-0. 1674 DZ=-0. 1716 I
| |
| AMVT CA=9 PT=326 DX=-0. 1412 DY=0.1991 DZ=-0. 0815 AMVT AMVT AMVT CA=10 CA=11 CA=12 PT=326 PT=326 PT=326 DX=-0. 2788 DX=-0. 1412 DX=-0.3120 DY=0.3 930 DY=0.1991 DY=0. 4398 DZ=-0 .1609 DZ=-0.0815 DZ=-0. 1800 I
| |
| I AMVT CA=13 PT=326 DX:-0.3120. DY=0. 4398 DZ=-0. 1800 AMVT CA=14 PT=326 DX=-0. 1899 DY=0.2678 DZ=-0.1097 AMVT CA=1 5 PT=326 DX=-0. 1613 DYý=0. 2275 DZ=-0. 0931 AMVT CA=1 6 PT=326 DX=-0.0939 DY=0. 1324 DZ=-0. 0542 I
| |
| AMVT CA=17 PT=326 DX=-0.0174 DY=0. 0246 DZ=-O.0101 AMVT CA=18 PT=326 DX=-0. 0174 DY=0.0246 DZ=-0.0101 AMVT CA=1 9 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 File No.: VY-16Q-307 Revision: 0 Page A14 of A51 I F0306-O1 RO I
| |
| | |
| U StructuralIntegrity 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
| |
| | |
| StructuraIntegrityAssociates, Inc.
| |
| I TANG PT=563 DZ=-6.92 TANG PT=565 DZ=-6.92
| |
| ---------------------
| |
| I
| |
| *END REGION 7B GEOMETRY FROM RHR SUPPLY VALVE TO PENET. NODE 565
| |
| ---------------------
| |
| ----------------- -------------
| |
| I
| |
| *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 I
| |
| *NOTE CODING FOR 4 INCH BYPASS STARTS HERE JUNC PT=152 CROS CD=27 I
| |
| MATL CD=376.316 BRAN PT=700 DX=-l.19 TANG PT=702 DX=-0.61 TANG PT=703 DX=-I.43 TE=4 EW=O I
| |
| MATL CD=403.316, BRAD PT=704 RA=0.5 MATL CD=376.316 TANG. PT=705 DZ=-5.08 EW=0 I
| |
| *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 I
| |
| TANG PT=708 DZ=0.34 TANG PT=709 DZ=0.38 JUNC PT=707 BRAN PT=710 DY=0.34 TE=I I
| |
| CROS CD=28 VALV PT=712 DY=0.71 MA=0.3669 PL=I VALV PT=715 DZ=-3.5 MA=0.1831 PL=3 JUNC PT=712
| |
| *AL=$Vl *LVE V2-54A$
| |
| I VALV PT=714 DY=0.71 PL=2 CROS CD=27 TANG PT=723 DY=4.19 MATL CD=403.316 I
| |
| BRAD PT=716 RA=0.5 MATL CD=376.316 TANG PT=718 DX=I.48 TANG PT=720 DX=0.56 I
| |
| BRAN PT=176 DX=I.19 TE=4
| |
| ************CODING FOR STRUTS RDA5 AND VABI FOLLOW JUNC PT=170 CROS CD=40 *OD=4.5 inch I
| |
| RIGD PT=725 DP=0 DX=-0.583 DY=I,84 *AL=$RDAS$
| |
| CROS CD=41 RIGD PT=715 DP=0 DX=-2.67 DY=-0.79 RIGD PT=721 DP=0 DY=-I.05
| |
| *OD=2.875 inch
| |
| *AL=$VABI$
| |
| I I
| |
| *************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
| |
| *-------------------
| |
| File No.: VY-16Q-307 Revision: 0 Page A16 of A5l I F0306-01 RO i
| |
| | |
| K StructuralIntegrityAssociates, 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 PTý614 DZ=-I0.38 EW=I MATL CD=403.316 BRAD PTý615 RA=10 EW=1 S MATL CDý376. 316 TANG PT=620 DX=5.98 DZ=-3.45 EW=1
| |
| *NOTE
| |
| *NOTE VARIABLE SPRING H104 AT NODE 620
| |
| * 3 *NOTE
| |
| *NOTE VALVE V10-81A DATA FROM 5920-4590 WEIGHT - 6845.#
| |
| *NOTE WEIGHT APPLIED AT ESTIMATED CENTER OF GRAVITY (NODE 623)
| |
| CROS CDý30 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 StructuralIntegrityAssociates, Inc.
| |
| I
| |
| *NOTE
| |
| *NOTE VARIABLE SPRING HI05 AT NODE 655 I
| |
| *NOTE VALV PT=660 DX=-1.79 PL=2
| |
| *NOTE SPEC CHANGE TO CARBON STEEL MATL CD=106 EW=1 I
| |
| CROS CD=29 TANG PT=661 DX=-I TANG PT=663 DX=-3.31 BRAD PT=665 RA=2 EW=1 EW=1 I 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 I
| |
| *--------------------------
| |
| *END REGION
| |
| --------------------
| |
| 9B GEOMETRY FOR RHR RETURN FROM VALVE NODE 660 TO PENET. NODE 675 I
| |
| *--------------------------
| |
| ***STRESS INDICES AT CROSS POINT
| |
| -------------------- i INDI AT=210 AF=195 B1=0.5 C1=1 K1=4 B2=2.256 C2=3.024 K2=1 C3=1 K3=1 CP=0. 5 INDI INDI INDI AT=210 AT=210 AT=210 AF=215 AF=240 AF=260 B1=0.5 B1=0.5 B1=0.5 C1=1 K1=4 C1=1 K1=4 C1=1 K1=4 B2=2.256 82=1.805 B2=1.805 C2=3.024 C2=3.024 C2=3.024 K2=1 C3=1 K3=1 CP=0. 5 K2=1 C3=1 K3=1 CP=0.5 K2=1 C3=1 K3=1 CP=0. 5 I
| |
| *--------------------
| |
| ***
| |
| RSTN SUPPORTS
| |
| * ---------------------------
| |
| PT=675 DX=I SP=16000 *RHR SUPPLY PENET.
| |
| I RSTN PT=675 DY=1 SP=16000 *RHR SUPPLY PENET.
| |
| RSTN PT=675 DZ=I SP=23000 *RHR SUPPLY PENET.
| |
| ROTR PT=675 RX=1 SP=300000 *RHR SUPPLY PENET.
| |
| ROTR ROTR RSTN PT=675 PT=675 PT=565 RY=I RZ=1 DX=I1 SP=300000 SP=340000 SP=16000
| |
| *RHR
| |
| *RHR
| |
| *RHR SUPPLY SUPPLY SUPPLY PENET.
| |
| PENET.
| |
| PENET.
| |
| I RSTN PT=565 DY=1 SP=16000 *RHR SUPPLY PENET.
| |
| RSTN PT=565 DZ=I SP=23000 *RHR SUPPLY PENET.
| |
| ROTR PT=565 RX=I SP=300000 *RHR SUPPLY PENET.
| |
| ROTR ROT.R PT=565 PT=565 RY=1 RZ=1 SP=300000 SP=340000
| |
| *RHR
| |
| *RHR SUPPLY SUPPLY PENET.
| |
| PENET.
| |
| I PT=12 DZ=-I *AL=$SNUBBER SS-7A-I$
| |
| I SNUB SP=1000 DX=1 SP=1000 *AL=$SNUBBER SNUB PT=12 SS-7A-2$
| |
| PT=190 DX=-1 SP=1000 *AL=$SNUBBER SS-6-Al$
| |
| SNUB PT=190 DZ=1 SP=1000 *AL=$SNUBBER SS-6-A2$
| |
| VSUP PT=20 CSUP PT=27 DY=l DY=I FO=24.8 FO=8. 3 SP=2.664 KP=0.01
| |
| *AL=$VARI.
| |
| *AL=$CONST.
| |
| SUPT. HA-1$
| |
| SUPT. H-8-Al$
| |
| I PT=42 DY=I F0=8. 3 KP=0.01 *AL=$CONST.
| |
| I CSU P SUPT. H-8-A2$
| |
| CSUP PT=56 DY=I FO=18.05 KP=0.01 *AL=$CONST. SUPT. HA3 FOR PUMPS CSUP PT=69 DY=I FO=18.0 KP=0.01 *AL=$CONST. SUPT. HA4 FOR PUMPS CS UP PT=63 DY=I FO=18. 02 KP=0. 01 *AL=$CONST. SUPT. *HA5 FOR PUMP$
| |
| CSU P PT=160 DY=-I FO=11. 8 KP=0 .01 *AL=$CONST. SUPT. HA-9 & HA-10S CSUP PT=705 DY=1 po=0. 960 KP=0.01 *AL=$CONST. SUPT. HA-lI ON 4 INCH BYPASS$
| |
| VSUP PT=184 DY:l FO=36.0 SP=3.542 *AL=$VARI. SUPT. HA-2$
| |
| VSUP PT=343 DY=l FO=7. 1 SP=3. 014 *AL=$VARI. SUPT. HAI3$
| |
| File No.: VY-'16Q-307 Revision: 0 Page AI8 of A51 I F0306-OI RO I
| |
| | |
| V Structural integrityAssociates, Inc.
| |
| VSUP PT=313 DY=l FO=7.1 SP=3.014 *AL=$VARI. SUPT. HAI4$
| |
| VSUP PT=530 DY=l SP=9.420 FO=26.0 *AL=$HANGER H109 RHR SUPPLY VALVE$
| |
| VSUP PT=620 DY=l SP=7.084 FO=14.9 *AL=$HANGER H104 RHR RETURN VALVE$
| |
| VSUP PT'=655 DY=l SP=4.710 FO=22.0 *AL=$HANGER H105 RHR RETURN VALVES RSTN PT=15 DY=0.7071 DZ=-0.7071 SP=6000 *RECIRC PUMP RSTN PT=16 DX=-0.707l DY='0.7071 SP=6000 *RECIRC PUMP ENDP RHR 15.inp IDEN JB=3 *Job number (1 to 999 9)
| |
| CD=I *I=ASME Class 1 GR=-Y *Direction of gravit y VA=0 *0=Calculate 2=Verify IU=l *Input units 1=USA OU=1 *Output units l=USA CH=$ *Delimiter character AB=T *FREE errors = abort PL=$Vermont Yankee$
| |
| EN=$RVP$
| |
| TITL BL=3 *Modeling option:
| |
| * 3 = uniform mass for static analysis lumped mass for dynamic analysis
| |
| * rotational inertia ignored GL=I *Report forces/moment .0=Global l=Local 2=G et L SU=l *Support summary 0=No l=Yes 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=$SEISMIC$
| |
| **** THERMAL CYCLE LOAD CASES****
| |
| LCAS RF=0 CA=1 TY=0 TI=$LC-l$ *TC-l LCAS RF=0 CA=2 TY=0 TI~=$LC-2$ *TC-2 LCAS RF=0 CA=3 TY=0 TI=$LC-3$ *TC-3 LCAS RF=0 CA=4 TY=0 rI=$LC-4$ *TC-4 LCAS RF=0 CA=5 TY=0 [rI=$LC-5$ *TC-5 LCAS RF=0 CA=6 TY=0, TI=-$LC-6$ *TC-6 LCAS RF=0 CA=7 TY=0 rI=$LC-7$ *TC-7 LCAS RF=0 CA=8 TY=0 rI=$LC-8$ *TCý8 LCAS RF=0 CA=9 TY=0 CI=$LC-9$ *TC-9 LCAS RF=0 CA=f0 TY=0 Tl=$LC-10$ *TC-10 LCAS RF=0 CA=I1 TY=0 T I=$ LC -11$ *TC-II LCAS RF=O CA=12 TY=0 TI=$LC-12$ *TC-12 LCAS RF=0 CA=13 TY=0 TI=$LC-13$ *TC-13
| |
| .LCAS RF=0 CA=14 TY=0 TI=$LC-14$ *TC-14 LCAS RF=0 CA=I 5 TY=0 TT=$LC-15$ *TC-15 LcAs RF=0 CA=16 TY=0 TT=$LC-16$ *TC-16 LCAS RF=0 CA=17 TY=0 TI=$LC-1?$ *TC-17 LCAS RF=0 CA=18 TY=0 TI=$LC-18$ *TC-18 LCAS RF=0 CA=I 9 TY=0 TI=$LC-19.$ *TC-19 LCAS RF=0 CA=20 TY=0 TI=$LC-20$ *TC-20 LCAS RF=0 CA=21 TY=0 TI=$LC-21$ *TC-21 LCAS RF=0 CA=22 TY=0 TI=$LC-22$ *TC-22 File No.: VY-16Q-307 Page A19 of A51 Revision:. 0 F0306-01 RO
| |
| | |
| StructuralIntegrityAssociates, Inc. I LCAS RF=0 CA=23 TY=0 TI=$LC-23$ *TC-23 I
| |
| LCAS RF=0 CA=24 TY=0 TI=$LC-24$
| |
| I
| |
| *TC-24 LCAS RF=0 CA=25 TY=0 TI=$LC-25$ *TC-25
| |
| **** WEIGHT CASES****
| |
| LCAS CA=101 LCAS CA=102 RF=I RF=2 TY=3 TY=4 TI=$OPERATING WEIGHT$
| |
| TI=$HYDROTEST WEIGHT$
| |
| I THERMAL TRANSIENT CASES**** I TCAS CA=201 TI=$Design Hydrotest (+)
| |
| TCAS TCAS TCAS CA=202 TI=$Design Hydrotest (-)
| |
| CA=203 TI=$Startup CA=204 TI=$TRoll & Inc. PWRI I
| |
| I TCAS CA=205. TI=$TRo11 & Inc. PWR2 TCAS CA=206 TI=$LOFWH+TT PWRI TCAS CA=207 TI=$LOFWH+TT:PWR2 TCAS CA=208 TI=$LOFWH+PFWHTR Bypl CA=209 TI=$LOFWH+PFWHTR Byp2 TCAS TCAS TCAS TCAS CA=210 TI=$LOFWP, ISO Cl DN 1 CA=211 TI=$LOFWP, ISO Cl UP 1 CA=212 TI=$LOFWP, ISO Cl DN 2 I
| |
| TCAS TCAS TCAS TCAS CA=213 TI=$LOFWP, ISO Cl UP 2 CA=214 TI=$Reduction to 0% PWR CA=215 TI=$Shutdownl CA=216 TI=$Shutdown2 I
| |
| TCAS TCAS TCAS CA=217 TI=$Shutdown3 CA=218 TI=$Shutdown4 CA=219 TI=$Code Hydrotest I
| |
| TCAS CA=220 TI=$RHR Initiation UP TcAs CA=221 TI=$RHR Initiation DN TCAS CA=222 TI=$Inadvert. Inj. DOWN TCAS CA=223 TI=$Inadvert. Inj. UP TCAS CA=224 TI=$Single Relief BD DN TCAS CA=225 Ti=$Single Relief BD UP I
| |
| SEISMIC CASES****
| |
| RCAS CA=103 EQ=3 EV=l TY= .SU=I LO=l FX=l FY=l I
| |
| FZ=l TI=$OBE INERTIA$
| |
| **
| |
| ****
| |
| C**************************
| |
| LOAD COMBINATION CASES
| |
| * I CCAS CCAS CCAS RF=1 RF=I RF=l CA=104 ME=l FL=l CA=401 SS=l ME=1 EQ=3 CA=402 SS=I ME=3 F1=1 Cl=103 Cl=101 C1=103 CY=l0 C2=103 C2=1 TI=$OBE$
| |
| TI=$EQUATION 9 LEVEL B$
| |
| TI=$NORMAL+OBE$
| |
| I CCAS RF=I CA=403 SS=1 ME=3 F1=-I C1=103 C2=1 TI=$NORMAL-OBE$
| |
| **** LOAD SETS****
| |
| I
| |
| **********
| |
| LSET LSET RF=l RF=2 FC=0 FC=0 RP=I RP=I CY=120 CY=120 PR=I PR=2 MO=l MO=2 TR=201 TR=-202 TI=$Design Hydrotest (+)LS-I$
| |
| TI=$Design Hydrotest (-)LS-2$
| |
| I LSET RF=3 FC=0 RP=1 CY=300 PR=3 MO=3 TR=203 TI=$Startup LS-3$
| |
| LSET RF=3 File No.: VY-16Q-307 FC=0 RP=1 CY=579 PR=4 MO=4 TR=-204 TI=$TRoll & Inc. PWR1 LS-4$
| |
| Page A20 of A51 I
| |
| Revision: 0 F0306O01 RO I
| |
| | |
| C StructuralIntegrityAssociates, Inc.
| |
| I LSET RF=4 FC=0 RP=1 CY=579 PR=5 MO=5 TR=-205 TI=$TRoll & Inc. PWR2 LS-5$
| |
| LSET RF=4 FC=0 RP=1 CY=20 PR=6 MO=6 TR=206 TI=$LOFWH+TT PWRI LS-6$
| |
| T.ET RPFA FC=O PP== CY=2 DPR=7 M0=7 TR=-207 TI=$LOFWH+TT PWR2 LS-7$
| |
| LSET RF=5 FC=0 RP=I CY=70 PR=8 MO=8 TR=-208 TI=$LOFWH+PFWHTR Bypl LS-8$
| |
| LSET RF=5 FC=0 RP=I CY=70 PR= 9 MO=9 TR=209 TI=$LOFWH+PFWHTR Byp2 LS*-9$
| |
| LSET RF=5 FC=0 RP=I CY=70 PR=10 MO=10 TR=-210 TI=$LOFWP, ISO Cl DN 1 LS-10$
| |
| LSET RF=11 FC=0 RP=I1 CY=20 PR=I1 MO=II TR=211 TI=$LOFWP, ISO Cl UP 1 LS-11$
| |
| LSET RF=11 FC=0 RP=1 CY=20 PR=12 MO=12 TR=-212 TI=$LOFWP, ISO Cl DN 2 LS-12$
| |
| LSET RF=3 E'C=0 RP=1 CY=10 PR=13 MO=13 TR=213 TI=$LOFWP, ISO Cl UP 2 LSL-135 LSET RF=3 FC=0 RP=1 CY=300 PR=14 MO=14 TR=214 TI=$Reduction to 0% PWR LS-14$
| |
| LSET RF=5 FC=0 RP=I CY=300 PR=15 MO=15 TR=-215 TI=$Shutdownl LS-15$
| |
| LSET RF=15 FC=0 RP=1 CY=300 PR=16 MO=16 TR=-216 TI=$Shutdown2 LS-16$
| |
| LSET RF=16 FC=0 RP=I CY=300 PR=17 MO=17 TR=-217 TI=$Shutdown3 LS-17$
| |
| LSET RF=20 FC=0 RP=I CY=300 PR=18 MO=18
| |
| /
| |
| TR=-218 TI=$Shutdown4 LS-18$
| |
| RP=1 LSET RF=19 FC=0 CY=1 PR=19 MO=19 TR=219 TI=$Code Hydrotest LS-19$
| |
| LSET RF=20 FC=0 RP:I CY-300 PR=20 MO=20 TR=220 TI=$RHR Initiation UP LS-20$
| |
| LSET RF=2 0 FC=0 RP=I CY=300 PR=21 MO=21 TR=-221 TI=$RHR Initiation DN LS-215 RP=1 I LSET RF=5 FC=0 CY=0 PR=22 MO=22 TR=-222 TI=$Inadvert. Inj. DOWN LS-22$
| |
| RP=1 LSET RF=5 FC=0 RP=1 CY=0 PR=23 MO=23 TR=223 TI=$Inadvert. Inj. UP LS-23$
| |
| RF=2 3 PR=24 TI=$Single Relief BD DN LS-24$
| |
| LSET FC=0 RP=I CY=0 MO=24 TR=-224 LSET RF=2 4 FC= 0 CY=0 PR=25 MO=25 TR=225. TI=$Single Relief BD UP LS-255 LSET RF=2 FC=0 CY=5 FL=I PR=2 MO=402 TI=$NORMAL+OBE LS-26$
| |
| LSET RF=2 FC=0 CY=5 FL=1 PR=2 MO=403 TI=$NORMAL-OBE LS-275
| |
| *FATG AT=500 AF=502
| |
| *FATG AT=600 AF=602
| |
| **** RESPONSE SPECTRA****
| |
| SPEC FS=OBE EV=I ME=3 FP=0 TI=$RESPONSE$
| |
| LV=I DX=I DY=I DZ=1 DI=X 0.30/0.100 0.40/0.100 0.90/0.20(0 1.25/0.400 2.25/0.450 2.30/0.700 3.30/0.700 4.40/0.750 4.41/0.90 0 4.75/1.100 5.20/1.100 5.80/1.600 8.70/1.600 12.00/0.650 17.00/0.40(00120.00/0.350 30.00/0.350 36.00/0.350 DI=Y 01 0.30/0.030 0.40/0.030 0.50/0.05(0 0.60/0.075 1.00/0.075 1.20/0.100 2.00/0.220 2.40/0.350 3.50/0.35C 3.60/0.300 5.30/0.300 5.75/0.330 8.25/0.330 8.75/0.250 17.50/0.25( 25.00/0.120 30.00/0.120 36.00/0.120 DI=Z 0.30/0.100 0.40/0.100 0.50/0.130 0.90/0.150 1.00/0.250 1.60/0.250 1.90/0.600 3.50/0.600 3.75/0.700 4.40/0.700 4.50/0.800 6.25/1.500 8.50/1.500 12.50/0.500 20.00/0.350 30.00/0.350 36.00/0.350 MATERIAL PROPERTIES *
| |
| *** ***A* ** *G******0B,
| |
| * ASTM A-106 Grade B, PIPE
| |
| * MATH CD=106 EX=0 TY=1 *C-Si MATD TE=70 EH=29. 5 EX=0. 0 SM=20.0 SY=35 MATO TE=100 EH=2 9.3 EX=0.20 SM=20. 0 SY=35 MATD TE=200 EH=28.8 EX=I.00 SM=20.0 SY=32. 1 MATD TE=300 EH=2 8.3 EX=l. 90 SM=20.0 SY=31 MATD TE=400 EH=2 7.7 EX=2.80 SM=20. 0 SY=29. 9 MATD TE=500 EH=27.3 EX=3.70 SM=18. 9 SY=28.5 MATD TE=600 EH=2 6. 7 EX=4.70 SM=17 .3 SY=26. 8
| |
| * ASME SA-376 Grade TP316, PIPE
| |
| * MATH CD=376.316 EX=0 TY=4 *16Cr-12Ni-2Mo File No.: VY-16Q-307 Page A21 of A51 Revision: 0 F0306-01RO
| |
| | |
| StructuralIntegrityAssociates, Inc. .
| |
| I MATD MATD MATD TE=70 TE=l00 TE=200 EH=28.3 EH=28. 1 EH=27. 6 EX=0. 0 EX=0. 30 EX=l. 40 SM=20.0 SM=20.0 SM=20.0 SY=30.0 SY=30.0 SY=25.9 I
| |
| MATD TE=300 EH=27.0 EX=2.50 SM=20.0 SY=23.4 MATD MATD MATD TE=400 TE=500 TE=600 EH=2 6.5 EH=25. 8 EH=25.3 EX=3.70 EX=5.00 EX=6.30 SM=19.3 SM=18.0 SM=17.0 SY=21.4 SY=20.0 SY=18.9 I
| |
| * ASME SA-403 Grade WP316, ELBOWS
| |
| * MATH CD=403.3] 16 EX=0 MATD TE=70 MATD TE=100 EH=28.3 EH=28.1 TY=4 EX=0. 0
| |
| *16Cr-12Ni-2Mo SM=20.0 EX=0. 30 SM=20.0 SY=30.0 SY=30.0 I
| |
| MATD TE=200 EH=27.6 EX=1. 40 SM=20.0 SY=25.9 MATD TE=300 MATD TE=400 MATD TE=500 EH=27.0 EH=26.5 EH=25.8 EX=2.50 EX=3.70 EX=5.00 SM=20.0 SM=18.7 SM=17.5 SY=23.4 SY=21.4 SY=20.0 I
| |
| MATD TE=600 EH=25.3 EX=6. 30 SM=16.4 SY=18.9 Cross Sectional Properties CROS CD=1
| |
| *CROS CD=2 OD=50.0 SO=1 OD=37.85 WT=8.87 ST=I. 0 WT=6. 1 MA=3977.2 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| MA=2122.2
| |
| *RECIRCULATION OUTLET NOZZLE
| |
| *CALC. PER GE SPEC. NO. 23A5569 [31 I
| |
| CROS CD=3 SO=1 ST=I. 0 OD=28. 875 WT=1.56 SO=l ST=I. 0 MA=484. 9 *CALC. PER GE SPEC. NO. 23A5569 [3] I CROS CD=4 OD=28.638 WT=I.45 MA=450.4 *CALC. PER GE SPEC. NO. 23A5569 [31 CROS CD0=5 SO=l ST=I.0 OD=28.169 WT=1. 244 SO=l ST=1 .0 MA=386. 1 *CALC. PER GE SPEC. NO. 23A5569 [3] I CROS CD=7 OD=28.166 WT=2.125 MA=0. 001 *VALVE CROS CD=8 SO=1 OD=42, 507 SO=. 001 ST=I .0 WT=2.486 ST=. 001 KL=1 MA=0. 001 KL=1
| |
| *PUMP I CROS CD=11 OD=6. 625 WT=0. 432 MA=O. 001 *PUMP RIGID STRUTS CROS CD=13 so=o.001 OD=28.339 SO=1 ST=0.001 WT=1. 339 ST=1 KL=I MA=415. 1 *CALC. PER GE SPEC. NO. 23A5569 [3] I CROS CD=14 OD=28,339 WT=2. 67. MA=0.001 *VALVE CROS CD=15 SO=1 OD=12, 748 50=1 ST=1. 0 WT=0. 685 ST=1. 0 KL=1 MA=I03.4 *CALC. PER GE SPEC. NO. 23A5569 [3] I CROS CD=16 OD=14,17 WT=1.395 MA=207. 5 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| CROS CD=17 SO=l OD=15.5 ST=I. 0 WT=2 ST=I .0 MA=307. 7 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| I CROS CD=18 OD=21.88 WT=4. 06 MA=8 03.2 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| CROS CD=19 SO=I OD=28.25 SO=1 ST=I .0 WT=7.25 ST=I .0 MA=1673.1 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| I CROS CD=20 OD=21. 878 WT=I.043 MA=257 .2 *CALC. PER GE SPEC. NO. 23A5569 I
| |
| [3]
| |
| SO=l ST=1 .0 CROS CD=25 OD=20 WT=I.031 MA=221. 9 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO= ST=I CROS CD=26 OD=20 WT=1.875 MA=0.001 *VALVE CROS CD=27 SO=1 OD=4 .5 SO=1 ST=I WT=0. 3385 SThI KL=1 MA=2 3.2 KL=I
| |
| *CALC. PER GE SPEC.
| |
| *4 inch bypass line NO. 23A5569 [3]
| |
| I CD=28 OD=4. 5 WT=0. 67 *.VALVE V2-54A I
| |
| CROS MA=0.001 SO= ST=I KL=1 CROS CD=29 OD=24 WT=I.217 MA=316. 5 *CALC. PER GE SPEC. NO. 23A5569 [3]
| |
| SO=I ST=I CROS CD=30 OD=24 WT=2.43 MA=0.001 *VALVE File No.: VY-16Q-307 Revision: 0 Page A22 of A5lI. I F0306-01 RO I
| |
| | |
| Structural Integrity Associates, Inc.
| |
| [
| |
| SO=1 ST=1 KL=1 CROS CD=40 OD=4. 5 WT=0.3385 MA=0.001 *4 inch bypass STRUTS SO=-0.001. ST=0.001 KL=1 CROS CD=41 OD=2. 875 WT=0.276 MA=0.001 *STRUT RDA1, RDA5, & VBAI SO=0.001 ST=0.001 KL=1 CROS CD=42 OD=28.339 WT=1.339 MA=0.001 *RIGID FROM RECIRC ELBOW TO RDAI STRUT SO=0.00l ST=0.001 KL=1
| |
| * 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 76.316 CROS CD=1 COOR PT=3 AX =0 AY=0 AZ=0 ANCH PT=3 AMVT C.A=I PT='3 DX=0. 0000 DY=0. 0176 DZ=-0. 0201 AMVT C]A=2 PT=3 DX=0. 0000 DY=0. 3141 DZ=-0. 3602 AMVT C;A=3 PT=3 DX=0. 0000 DY=0.3112 DZ=-0. 3568 AMVT C;A=4 PT=3 DX=0. 0000 DY=0. 2995 DZ=-0. 3434 AMVT CiA= 5 PT=3 DX=0. 0000 DY=0. 3112 DZ=-0. 3568 AMVT CiA=6 PT=3 DX=0. 0000 DY=0.2995 DZ=-0. 3434 AMVT CiA=7 PT=3 DX=0. 0000 DY=0.2922 DZ=-0.3350 AMVT CiA=8 PT=3 DX=0. 0000 DY=0.2995 DZ=-0 .3434 AMVT CiA=9 PT=3 DX=0. 0000 DY=0. 1422 DZ=-0.1630 AMVT C)%=10 PT=3 DX=0. 0000 DY=0.2807 DZ=-0.3218 AMVT C) PT=3 DX=0. 0000 DY=0. 1422 DZ=-0. 1630 AMVT C) PT=3 DX=0. 0000 DY=0. 3141 DZ=-0.3602
| |
| -AMVT C)A--13 PT=3 DX=0. 0000 DY=0. 3141 DZ=-0 .3602 AMVT C)A=I4 PT=3 DX=0.0000 DY=0 1928 DZ=-0.2521 AMVT C)A=I5 PT=3 DX=0. 0000 DY=0. 1624 DZ=-0. 1986 AMVT C) PT=3 DX=0. 0000 DY=0. 0946 DZ=-0. 1084
| |
| .AMVT C) PT=3 DX=0.0000 DY=0. 0176 DZ=-0.0201 AMVT C1 *=18 PT=3 DX=O. 0000 DY=0. 0176 DZ=-0.0201 AMVT C1 4=19 PT=3 DX=0. 0000 DY=0. 0946 DZ=-0. 1084 AMVT C7 4=20 PT=3 DX=0. 0000 DY=0. 0946 DZ=-0. 1084 AMVT C1 4=21 PT=3 DX=0.0000 DY=0. 0361 DZ=-0.0413 1=22 AMVT C1 PT=3 DX=0. 0000 DY=O0.2995 DZ=-0. 3434 AMVT C1%=24 --23 PT=3 DX=0. 0000 DY=0. 1928 DZ=-0.2521 AMVT Cr PT=3 DX=0. 0000 DY=0. 0176 DZ=-0. 0201 File No.: V,Y-16Q-307 Page A23 of A51 Revision: 0 F0306-O1RO
| |
| | |
| StructuralIntegrityAssociates, Inc. U I
| |
| TANG PT=805 CROS CD=2 TANG PT=806 DZ=-1.017 DZ=-0.823 EWI=1 EW=1 m
| |
| CROS CD=3 TANG PT=807 CROS TANG PT=808 CD=4 DZ=-0.58 DZ=-o.47 EW=I1 I
| |
| CROS CD=5 TANG PT=5 MATL CD=403.316 BRAD PT=7 DZ=-5.59 EW=1 RA=3.5 EW=1 U
| |
| I MATL CD=376.316 TANG PT=9 DY=-6.69 EW=Il TANG PT=500 DY=-2.31
| |
| -----------------------------------
| |
| *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 JUNC PT=40 CROS CD=5 MA=1.132 I
| |
| 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 CD=8 RIGD PT=54 DX=I.06 DZ=1.06 RIGD PT=56 DX=1.06 DY=0.75 DZ=l .06 *NOTE CONSTANT SUPPORT HA3 AT NODE 56 JUNC PT=50 RIGD PT=66 DZ=-3.83 RIGD PT=69 DY=1 *NOTE CONSTANT SUPPORT HA4 AT NODE 69 JUNC PT=50 CROS CD=8 RIGD PT=60 DX=-3.83 RIGD PT=63 DY=l *CONSTANT SUPPORT HA5 AT NODE 63
| |
| * *** CODING FOR PUMP RIGID STRuJTS FOLLOW **
| |
| CODED FROM PUMP.CENTERLINE CR0S CD=11 JUNC PT=66 RIGD PT=15 DY=0.7071 DZ=-0.70)71 JUNC PT=.60 RIGD PT=16 DX=-0.7071 DY=0.70371
| |
| * *** END OF CODING FOR PUMP SUP'PORTS ***
| |
| *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 TO PIPE AT NODE 151 CROS CD=13 TANG PT=I52 DZ=I. 25 TANG PT=155 DZ=1 EW=1 CROS CD=14 VALV PT=160 PL=1 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=170 PL=2 DX=0.O 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=176 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=188 DY=1.51 TANG PT=189 DY=0.74 File No.: VY-16Q-307 Page A25 of A51 Revision: 0 F0306-OIRO
| |
| | |
| V StructuralIntegrityAssociates, Inc. I I
| |
| 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 I
| |
| INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG3B.INP JUNC PT=600 TANG PT=I95 DY=2.08 EW=1 I
| |
| 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 U
| |
| ----------------------
| |
| ---------------
| |
| *BEGIN REGION 5 TRANSIENT CARDS
| |
| *--------------------------------
| |
| ---------------
| |
| & GEOMETRY RISER TO NOZZLE NODE 336 I
| |
| *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 U
| |
| CROS MATL TANG CD=I3 CD=376.316 PT=215 DX=0.0 DY=2.59 DZ=0.0 EW=0 I
| |
| CRED PT=220 DY=1.29 AN=30 EW=l. *AL=$CONC. REDUCER$
| |
| CROS TANG TANG CD=I5 PT=330 DY=4.58 PT=335 DY=3.29 EW=l I
| |
| MATL CD=403.316 BRAD
| |
| *END PT=334 RA=l.5
| |
| ---------------------
| |
| EW=l REGION 5 GEOMETRY RISER TO NOZZLE NODE 336 I
| |
| *--------------------------
| |
| * ------------------------------
| |
| *BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO NOZZLE NODE 336 I
| |
| * ------------------------------
| |
| *GROUP 6 TO NOZZLE NODE 336 INCL FN=Z: \SISJ-PROJECTS\VY-16Q\RevO\REG6.INP I MATL CD=376.316 TANG CROS TANG PT=838 DX=3.875 CD=16 PT=837 DX=0.875 EW=I I
| |
| CROS CD=17 TANG CROS TANG PT=836 DX=0.37 EW=1 CD=18 PT=835 DX=0.53 EW=l I
| |
| CROS CD=19 TANG NOZZ AMVT PT=336 DX=0.704 PT=336 CA=I PT=336 EW=1 DX=-0.0201 DY=0.0246 DZ=0.0000 I
| |
| AMVT CA=2 PT=336 DX=-0.3602 DY=0.4398 DZ=0.0000 AMVT AMVT AMVT CA=3 CA=4 CA=5 PT=336 PT=336 PT=336 DX=-0.3568 DX=-0.3434 DX=-0.3568 DYý-0.4316 DY=0.4152 DY=0.4050 DZ=0.0000 DZ=0.0000 DZ=0.0000 I
| |
| AMVT CA=6 PT=336 DX=-0.3434 DY=0.2940 DZ=0.0000 AMVT AMVT AMVT CA=7 CA=8 CA=9 PT=336 PT=336 DX=-0.3434 PT=336 DX=-0.3350 DX=-0.1630 DY=0.3229 DY=0.2700 DY=0.1991 DZ=0.0000 DZ=0.0000 DZ=O.O0000 I
| |
| File No.: V SY-1I6Q-307 Revision: 0 Page A26 of A51 I
| |
| F0306-OI RO I
| |
| | |
| 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 366 l*
| |
| *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 StructuralIntegrityAssociates, Inc. I BRAD PT=365 RA=1.5 EW=1
| |
| -------------------
| |
| *END REGION 5 GEOMETRY RISER TO NOZZLE NODE 366
| |
| *---------------- -- I
| |
| -------------------------------
| |
| *BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY
| |
| * ------------------------------
| |
| *GROUP 6 TO NOZZLE NODE 366 TO NOZZLE NODE 366 I
| |
| INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP MATL TANG CD=376. 316 PT~=868 DX~=1.8 DZ=~-3.1 I
| |
| CROS CD=~16 TANG CROS TANG PT=867 DX=0.4375 DZý=-0.76 CD=17 PT=866 DX=0.185 DZ=-0.32 EW~1 EW=1 I
| |
| CROS CD=18 TANG CROS TANG PT=865 DX=0.265 DZ=-0.46 CD19 PT=366 DX=0.352 DZ--0.61 EW=I EW=1 I
| |
| NOZZ PT=366 AMVT AMVT AMVT CA=1 CA=2 CA=3 PT=366 PT=366 PT=366 DX=-0. 0101 DX=-0. 1800 DX=-0. 1783 DY=0. 0246 DY=0. 4398 DY=0. 4357 DZ=0.0174 DZ=0.3120 DZ=0. 3091 I
| |
| AMVT CA=4 PT=366 DX=-0. 1716 DY=0. 4193 DZ=0.,2974 AMVT AMVT AMVT CA=5 CA=6 CA=7 PT=366 PT=366 PT=366 DX=-0. 1783 DX=-0. 1716 DX=-0. 1674 DY=0.4357 DY=0. 4193 DY=0.4091 DZ=0. 3091 DZ=0. 2974 DZ=0.2902 I
| |
| AMVT CA=8 PT=366 DX=-0. 1716 DY=0. 4193 DZ=0.2974 AMVT AMVT AMVT CA=9 CA=10 CA11 PT=366 PT=366 PT=366 DX=-0. 0815 DX=-0. 1609 DX=-0. 0815 DY=0. 1991 DY=0. 3930 DY=0. 1991 DZ=0. 1412 DZ=0.2788 DZ=0. 1412 I
| |
| AMVT CA=I2 PT=366. DX=-0. 1800 DY=0.4398 DZ=0.3120 AMVT AMVT AMVT QA=13 CA=14 CA=15 PT=366 PT=366 PT=366 DX=-0. 1800 DX=-0. 1097 DX=-0. 0931 DY=0.4398 DY=0.2678 DY=0.2275 DZ=0.3120 DZ=0. 1899 DZ=0. 1613 I
| |
| AMVT CA=16 PT=366 DX=-0.0542 DY=0. 1324 DZ=0 .0939 AMVT CA=17 PT=366 DX=-0. 0101 DY=0. 0246 DZ=0. 0174 AMVT CA=I8 PT=366 DX=-0.0101 DY=0. 0246 DZ=0. 0174 AMVT CA=19 PT=366 DX=-0. 0542 DY=0. 1324 DZ=0.0939 AMVT AMVT AMVT CA=20 CA=21 CA=22 PT=366 PT=366 PT=366 DX=-0. 0101 DX=-0.0207 DX=-0. 1716 DY=0.0246 DY=0. 0505 DY-.0. 4193 DZ==0.0174 DZ=0.0358 DZ=0 .2974 I
| |
| AMVT AMVT CA=23 CA=24 PT=366 PT=3666 DX=-0. 1105 DX=-0.0101 DY=0. 2700 DY=0. 0246 DZ=0. 1915 DZ=0. 0174 I
| |
| * --------------------
| |
| *END REGION 6 GEOMETRY TO NOZZLE NODE 366
| |
| --------------------- I I
| |
| -------------------------------
| |
| *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 I
| |
| CROS CD=20 BRAN PT=260.DX=0.1786 File No.: VY-16Q-307 DY=0.0 DZ=-1.7 TE=2 Page A28 of A51 I
| |
| Revision: 0 F0306-OI RO I
| |
| | |
| i SStructuralIntegrityAssociates, 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 PTý316 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 PTý316 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 StructuralIntegrity Associates, Inc.
| |
| I I
| |
| AMVT AMVT AMVT CA=I3 CA=14 CA=15 PT=316 PT=316 PT=316 DX=-0.1800 DX=-O. 1097 DX=-O.0931 DY=0D.4398 DY=0.2678 DY=0.2275 DZ=-0.3120 DZ=-0.1899 DZ=-0. 1613 I
| |
| AMVT CA=16 PT=316 DX=O.0542 DY=0.1324 DZ=-0.0939 AMVT CA=17 PT=316 DX=-0. 0101 DY=0. 0246 DZ=-O. 0174 AMVT AMVT AMVT CA=18 CA=19 CA=220 PT=316 PT=316 PT=316 DX=-0. 0101 DX=-O.0542 DX=-0. 0101 DY=0.0246 DY=0. 1324 DY=0.0246 DZ=-0.0174 DZ=-0.0939 DZ=-0. 0174 I
| |
| AMVT AMVT AMVT CA=21 CA=22 CA=2 3 PT=316 PT=316 PT=316 DX=-0.0207 DX=-0. 1716 DX=-0. 1105 DY=0.0505 DY=0. 4193 DY=O0.2700 DZ=-0 .0358 DZ=-0.2974 DZ=-0. 1915 I
| |
| AMVT CA=24 PT=316 DX=-0.0101 DY=0. 0246 DZ=-0. 0174
| |
| *END REGION
| |
| ---------------------
| |
| 6 GEOMETRY TO NOZZLE NODE 316 I
| |
| -------------------------------
| |
| *BEGIN REGION 5 TRANSIENT
| |
| -------------------------------
| |
| CARDS & GEOMETRY RISER TO NOZZLE NODE 346 I
| |
| *GROUP 5 RISER TO NOZZLE NODE 346 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG5.INP JUNC PT=340 I
| |
| CROS CD=15 BRAN TANG MATL PT=342 DY=1.36 PT=344 DY=10.39 CD=403.316 TE=2 EW=0 I BRAD PT=345 RA=1.5 EW=1
| |
| ---------------------
| |
| *END REGION 5 GEOMETRY RISER TO NOZZLE NODE 346
| |
| *--------------------------
| |
| I
| |
| * ------------------------------
| |
| *BEGIN REGION
| |
| * ------------------------------
| |
| 6 TRANSIENT CARDS & GEOMETRY TO NOZZLE NODE 346 I
| |
| *GROUP 6 TO NOZZLE NODE 346 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\Rev0\REG6.INP MATL CD=376.316 I
| |
| TANG PT=848 DX=3.17 DZ=-1.83 CROS TANG CROS CD=16 PT=847 DX=0.758 DZ=-0.4375 CD=17 EW=1 I TANG PT=846 DX=0.32 DZ=-0.185 EW=1 CROS TANG CROS CD=18 PT=845 DX=0.46 DZ=-0.265 CD=19 EW=1 I TANG PT=346 DX=0.61 DZ=-0.352 EW=1 NOZZ PT=346 AMVT AMVT AMVT CA=1 CA=2 CA=3 PT=346 PT=346 PT=346 DX=-0. 0174 DX=-0. 3120 DX=-0. 3091 DY=0. 0246 DY=0.4 398 DY=0.4357 DZ=0.0101 DZ=0.1800 DZ=0.1783 I
| |
| AMVT AMVT AMVT CA=4 CA=5 CA=6 PT=346 PT=346 PT=346 DX=L0.2974 DX=-0. 3091 DX=-0.2974 DY=0.4193 DY=0. 4357 DY=0. 4193 DZ=0.1716 DZ=0 .1783 DZ=0.1716 I
| |
| AMVT CA=7 PT=346 DX=-0. 2902 DY=0. 4091 DZ=0. 1674 AMVT AMVT AMVT CA=8 CA= 9 CA=10 PT=346 PT=346 PT=346 DX=-0.2974 DX=-0. 1412 DX=-0. 2788 DY=0. 4193 DY=0. 1991 DY=0. 3930 DZ=0.1716 DZ=0.0815 DZ=0.1609 I
| |
| AMVT CA=11 PT=346 DX=-0. 1412 DY=0. 1991 DZ=0.0815 File No.: VY-16Q-307 Page A30 of A51 I
| |
| Revision: 0 F0306-OI RO I
| |
| | |
| 1 StructuralintegrityAssociates, Inc.
| |
| AMVT CA=I12 PT=346 DX='-0.3120 DY=0.4398 DZ=0.1800 AMVT CA=13 PT=346 DX=-0. 3120 DY=0.4398 DZ=0. 1800 AMVT CA=14 PT=346 DX=-0. 1899 DY=0. 2678 DZ=0. 1097 AMVT CA=15 PT=34 6 DX=-0. 1613 DY=0.2275 DZ=0.0931 AMVT CA=16 PT=346 DX=-0.0939 DY=0.1324 DZ='0.0542 AMVT CA=17 PT=346 DX=-0. 0174 DY=0.0246 DZ=0. 0101 AMVT CA=18 PT=346 DX=-0. 0174 DY=0. 0246 DZ=0. 0101 AMVT CA=19 PT=346 DX=-0. 0939 DY=0. 1324 DZ=0 -0542 AMVT CA=20 PT=346 DX=-0.0174 DY=0. 0246 DZ=0.0101 AMVT CA=21 PT=346 DX=-0. 0358 DY=O. 0505 DZ=0. 0207 AMVT CA=22 PT=346 DX=-0. 2974 DY=0. 4193 DZ=0. 1716 AMVT CA=2 3 PT=346 DX=-0. 1915 DY=0.2700 DZ=0.1105 AMVT CA=24 PT=346 DX=-0. 0174 DY=0. 0246 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 NOZZLE NODE 326
| |
| * ------------------------------
| |
| *GROUP 6 TO NOZZLE NODE 326 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP MATL CD=376. 316 TANG PT=828 DX=3.18 DZ=1.84 CROS CD=16 TANG PT=827 DX=0.758 DZ=0.4375 EW=1 CROS CD=17 TANG PT=826 DX=0.32 DZ"0.185 EW=1 CROS CD=18 TANG PT=825 DX: '0.46 DZ=0.265 EW=1 CROS CD=19 TANG PT=326 DX: :0.61 DZ=0.352 EW=1 NOZZ PT=326 AMVT CA=1 PT=326 DX"-0.0174 DY=0.0246 DZ=-0.0101 AMVT CA=2 PT=326 DX=-0. 3120 DY=O. 4398 DZ=-0. 1800 AMVT CA=3 PT=326 DX=-0.3091 DY=0. 4357 DZ=-0. 1783 AMVT CA=4 PT=326 DX=-0. 2974 DY=O. 4193 DZ=-0..1716 AMVT CA=5 PT=326 DX=-0. 3091 DY=0.4 357 DZ=-0. 1783 AMVT CA=6 PT=326 DX=-0. 2974 DY=0. 4193 DZ=-0. 1716 AMVT CA= 7 PT'326 DX=-0.2902 DY=0. 4091 DZ=-0. 1674 AMVT CA=8 PT=326 DX=-0.2974 DY=0. 4193 DZ=-0. 1716 AMVT CA= 9 PT=326 DX=-0. 1412 DY=0. 19 91 DZ=-0. 0815 AMVT CA=10 PT=326 DX=-0.2788 DY=0.3930 DZ=-0.1609 File No.: VY-16Q-307 Page A31 of A51 Revision: 0 F0306-OIRO
| |
| | |
| StructuralIntegrityAssociates, Inc. U I
| |
| AMVT CA=II PT=326 DX=-0.1412 DY=0.1991. DZ=-0.0815 AMVT AMVT AMVT CA=l2 CA=13 CA=14 PT=326 PT=326 PT=326 DX=-0.3120 DX=-0.3120 DX=-0.1899 DY=0.4398 DY=0.4398 DY=0.2678 DZ=-0.1800 DZ=-0.1800 DZ=-0.1097 I
| |
| 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 MATL CD=403.316 BRAD PT=515 DZ=-4.53 PT=520 RA=I.67 EW=I EW=l I
| |
| 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 JUNC RIGD PT=545 DX=-I.97 PT=545 PT=547 DY=2.5 PL=I I
| |
| 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
| |
| | |
| " StructuralIntegrityAssociates, 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 CD=27 MATL CD=376. 316 BRAN PT=700 DX=-1.19 TE=4 TANG PT=702 DX=-0.61 TANG PT=703 DX=-1.43 EW=0 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 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 PL=1 *AL=$VALVE V2-54A$
| |
| 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=1.48 TANG PT=720 DX=0.56 BRAN PT=176 DX=1.19 TE=4
| |
| ************CODING FOR STRUTS RDA5 AND VABI FOLLOW JUNC PT=170 CROS CD=40 *OD=4.5 inch RIGD PT=725 DP=0 DX=-0.583 DY==1.84 *AL=$RDA5$
| |
| CROS CD=41 *OD=2.875 inch RIGD PT=715 DP=0 DX=-2.67 DY=- -0.79 File No.: VY-16Q-307 Page A33 of A51 Revision: 0 F0306-01 RO
| |
| | |
| StructuralIntegrityAssociates, Inc. U
| |
| ~I RIGD PT=721 DP=O DY=-I.05 *AL=$VABI$
| |
| *************CODING CROS JUNC CD=42 PT=175 FOR RDAI STRUT FOLLOWS
| |
| *OD=28.339 inch I 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 TANG PT=614 DZ=-10.38 EW=l I
| |
| MATL CD=403.316 BRAD PT=615 RA=10 MATL CD=376.316 TANG PT=620 EW=1 DX=5.98 DZ=-3.45 EW=1 I
| |
| *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 I
| |
| MATL CD=403.316 BRAD PT=641 RA=2 EW=1 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 File No.: VY-16Q-307 Page A34 of A51 I Revision: 0 F0306-OIRO
| |
| | |
| I StructuralIntegrityAssociates, 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 SNUB PT=190 DZ=1 DX=-I SP=1000 SP=1000
| |
| .*AL=$SNUBBER SS-6-A2$
| |
| *AL=$SNUBBER SS-6-Al$
| |
| 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
| |
| | |
| StructuralIntegrityAssociates, Inc. U I
| |
| CSUP CSUP CSUP PT=27 PT=42 PT=56 DY= 1 DY=1 DY=~1 FO=8. 3 FO=8. 3 FO=18.05 KP=0.01 KP=0.01 KP=0.01
| |
| *AL=$CONST.
| |
| *AL=$CONST.
| |
| *ALý$CONST.
| |
| SUPT.
| |
| SUPT.
| |
| SUPT.
| |
| H-8-A1$
| |
| H-8-A2S HA3 FOR PUMPS I
| |
| CSUP PT=69 DY= 1 FO=18.0 KP=0 .. 01 *AL=$CONST. SUPT. HA4 FOR PUMPS CSUP PT=63 CSUP PT=160 CSUP PT=705 DY= 1 DY---1 bY=1 FO=18.02 FO=11. 8 FO=0.960 KP=0.01 KP=0.901 KP=0.01
| |
| *AL=$CONST.
| |
| *AL=$CONST.
| |
| *AL=$CONST.
| |
| SUPT.
| |
| SUPT.
| |
| SUPT.
| |
| HA5 FOR PUMPS HA-9 & HA-10S HA-lI ON 4 INCH BYPASS$
| |
| I vsuP PT=184 VSUP PT=343 VSUP PT=313 DY=1 DY=1 DY=1 FO=36.0 FO=7. 1 FO=7 .1 SP=3.542 SP=3.014 SP=3. 014
| |
| *AL=$VARI.
| |
| *AL$VARI.
| |
| *AL=$VARI.
| |
| SUPT.
| |
| SUPT.
| |
| SUPT.
| |
| HA-2$
| |
| HA13$
| |
| HA14$
| |
| I VSUP VSUP VSUP PT=530 PT=620 PT=655 DY=1 DY= 1 DY=1 SP=9.420 FO=26.0 SP=7.084 FO=14.9 SP=4.710 FO=22.0
| |
| *AL=$HANGER H109 RHR SUPPLY VALVES
| |
| *ALý$HANGER H104 RHR RETURN VALVE$
| |
| *ALý$HAN1GER H105 RHR RETURN VALVES I
| |
| 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 I Regl.inp I
| |
| *BEGIN REGION 1 TRANSIENT CARDS & GEOMETRY FROM RHR SUPPLY TO TEE
| |
| ------------------------------
| |
| OPER CA=1 T 1Eý00 PR=1100
| |
| --------------------
| |
| I OPER CA=2 TFE=100 PR=50 OPER OPER OPER CA=3 CA=4 CA=5 TFE=549 T'E=542 TE=526 PR=1010 PR=1010 PR=1010 I
| |
| OPER CA=6 T'E=542 PR=1010 OPER OPER OPER CA=7 CA=8 CA=9 T£E=526 T'E=516 T E=526 PR=1010 PR=1010 PR=1010 I
| |
| OPER CA=10 T E=300 PR=1135 OPER OPER OPER CA=11 CA=12 CA=13 T'E=500 T E=300 TE=549 PR=1135 PR=675 PR=1010 I
| |
| OPER CA=14 T E=549 PR=1010 OPER OPER OPER CA=15 CA=16 CA=17 T E=375 T E=330 T E=225 PR=170 PR=90 PR=0 I
| |
| OPER CA=18 T E=100 PR=0 OPER OPER OPER CA=19 CA=20 CA=21 TE=100 TE=225 T E=225 PR=1563 PR=0 PR=0 I
| |
| OPER CA=22 TE=130 PR=1010 OPER OPER OPER CA=23 CA=24 CA=25 T E=526 T E=375 T E=100 PR=1010 PR=200 PR=0 I
| |
| TRAN TRAN TRAN CA:201 CA=202 CA=203 IS=1 FS=1 IS=1 FS=1 IS=1 FS=1 IT=70 IT1=00 IT=100 FT=100 FT=100 FT=54 9 TT=1800 TT1=800 TT=16164 FL=16158 FL=2262 FL=2262 IP=15 FP=1115 TP=0 IP=1115 FP=65 TP=0 IP=65 FP=1025 TP=0 I
| |
| TRAN CA=204 IS=1 FS=1 IT=549 FT=542 TT=0 FL=3231E IP=1025 FP=1025 TP=O TRAN TRAN TRAN CA=205 CA=206 CA=207 IS=1 FS=1 IS=1 FS=1 IS=1 FS=1 IT=542 IT=526 IT=542 FT=526 FT=542 FT=526 TT=0 TT=900 TT=360 FL=3231(
| |
| FL=3231(
| |
| FL=3231(
| |
| IP=1025 FPP1025 IP=1025 FP=1025 IP=1025 FP=1025 TP=0 TP=0 TP=0 I
| |
| TRAN CA=208 IS=1 FS=I IT=526 FT=516 TT=0 FL=3231E IP=1025 FP=1025 TP=0 TRAN .CA=209 IS=1 FS=I IT=516 FT=526 TT=0 FL=3231E IP=1025 FP=1025 TP=0 File No.: VY-16Q-307 Revision: 0 Page A36 of A51 I F0306-01 RO I
| |
| | |
| StructuralIntegrityAssociates, Inc.
| |
| I TRAN CA=210 IS=1 FS=1 IT=526 FT=300 TT=220 FL=600 IP=1205 FP=1150 TP=0 TRAN CA=211 IS=1 FS=1 IT=300 FT=500 TT=1980 FL=600 IP=900 FP=1150 TP=0 TRAN CA=212 IS=1 FS=1 IT=500 FT=300 TT=180 FL=600 IP=1150 FP=690 TP=0 TRAN CA=213 IS=1 FS=1 IT=300 FT=549 TT=8964 FL=16158 IP=255 FP=1025 TP=0 TRAN CA=214 IS=1 FS=1 IT-=526 FT=549 TT=0 FL=32316 IP=1025 FP=1025 TP=0 TRAN CA=215 IS=1 FS=1 IT=549 FT=375 TT=6264 FL=16158 IP=1025 FP=185 TP=0 TRAN CA=216 IS=1 FS=1 IT=375 FT=330 TT=600 FL=16158 IP=185 FP=105 TP=0 TRAN CA=217 IS=1 FS=1 IT=330 FT=225 TT=3780 FL=16158 IP=105 FP=15 TP=0 TRAN CA=218 IS=1 FS=1 IT=225 FT=100 TT=4500 FL=22858 IP=1.5 FP=15 TP=0 TRAN CA=219 IS=1 FS=1 IT=100 FT=100 TT=O FL=2262 IP=40 FP=1578 TP=0 TRAM CA=220 TRAN CA=221 TRAM CA=222 IS-I FS=1 IT=526 FT=130 TT=0 FL=32316 IP=1025 FP=1025 TP=0 TRAN CA=223 IS=1 FS=1 IT=130 FT=526 TT=0 FL=32316 IP=1025 FP=1025 TP=0 TRAN CA=224 IS=1 FS=1 IT=526 FT=375 TT=600 FL=32316 IP=1025 FP=215 TP=0 TRAN CA=225 IS=1 FS=1 IT=375 FT=100 TT=9900 FL=32316 IP=215 FP=15 TP=0 PAIR CA=201 ( 0=8. 3 mI=0. i40 EX=8.5 *Tavg=85.0 PAIR PAIR CA=202 C O=8.3 DI=0. 140 EX=8.5 *Tavg=100.0 PAIR CA=203 C:0=9.4 DI=0.151 EX=8.5 *Tavg=324.5 PAIR cA=204 CO=1 0. 5 DI=0.162 EX=8.5 *Tavg=545.5 PAIR CA=205 CO=10.4 DI=0.161 EX=8.5 *Tavg=534.0 PAIR CA=206 CO=10. 4 DI=0.l161 EX=8.5 *Tavg=534.0 CA=207 CO=10.4 DI=0. 161 EX=8.5 *Tavg=534.0 PAIR PAIR CA=208 CO=10. 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 CA=212 CO=9.8 DI=0.155 EX=8.5 *Tavg=400.0 PAIR CAý213 CO=9.9 DI=0.156 EX=8.5 *Tavg=424.5 PAIR 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 CA=217 CO=9.2 DI=0. 149 EX=8.5 *Tavg=277.5 PAIR PAIR CA=218 CO=8.7 DI=0.143 EX=8.5 *Tavg=162.5 CA=219 CO=8.3
| |
| * DI=0.140 EX=8.5 *Tavg=100.0
| |
| *PAIR DI=0. 14 6
| |
| *PAIR CA=220 CO=9.0 EX=8.5 *Tavg=225.0 D01=0. 14 DI=0. 1466 CA=221 CO=9.0 EX=8.5 *Tavg=225.0 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 Reg2.inp
| |
| * REGION ------------------------------------------------
| |
| *BEGIN REGION 2 TRANSIENT CARDS & GEOMETRY FROM RI-R SUPPLY TEE TO PUMP
| |
| ------------------------------------------------------
| |
| OPER CA=1 TE=100 PR=1100 OPER CA=2 TE=100 PR=50 OPER CA=3 TE=549 PR=1010 OPER CA=4 TE=542 PR=1010 OPER CA=5 TE=526 PR=1010 OPER CA= 6 TE=542 PR=1010.
| |
| OPER CA=7 TE=526 PR=1010 OPER CA=8 TE=516 PR=1010 OPER CA= 9 TE=526 PR=1010 OPER CA=10 TE=300 PR=1135 OPER CA=11 TE=500 PR=1135 OPER CA=12 TE=300 PR=675 File No.: VY-16Q-307 Page A37 of A51 Revision: 0 F0306-OIRO
| |
| | |
| V Structural Integrity Associates, Inc. I OPER CA=13 TE=549 PR=1010 I
| |
| *OPER OPER OPER OPER CA=14 CA=1I5 CA=16 CA=1 7 TE=549 TE=375 TE=330 TE=225 PR=1010 PR=1 70 PR=90 I
| |
| PR=O I
| |
| OPER CA=18 TE=100 PR=0.
| |
| OPER CA=1 9 TE=100 PR=1563 OPER CA=20 TE=225 PR=0 OPER CA=21 TE=225 PR=0 OPER OPER OPER OPER CA=22 CA=23 CA=24 CA=25 TE=130 TE=52 6 TE=375 TE=100 PR=1010 PR=1010 PR=200 PR=0 I
| |
| TRAN TRAN TRAN CA=201 CA=202 CA=203 IS=1 FS=1 IT=70 FT=100 13=1 FS=1 IT=100 FT=100 I3=1 FS=1 IT=100 FT=5 49 TT=1800 TT=1800 FL=2262 FL=2262 IP=15 FP=1115 IP=1115 FP=65
| |
| .TP=0 TP=0 I
| |
| TRAN TT=16164 FL=16158 IP=65 FP=1025 TP=0 TRAN TRAN TRAN CA=204 CA=205 CA=206 IS=1 FS=1 IT=549 FT=542 IS=1 FS=1 IT=542 FT=526 IS=1 FS=1 IT=526 FT=542 TT=0 TT=0 TT=900 FL=3231( IP=1025 FP=1025 FL=3231E IP=1025 FP=1025 FL=3231E IP=1025 FP=1025 TP=0 TP=0 TP=0 I
| |
| TRAN CA=207 IS=1 FS=1 IT=542 FT=526 TT=360 FL=32316 IP1=025 FP=1025 TP=0 TRAN TRAN TRAN CA=208 CA=209 CA=210 IS=1 FS=1 IT=526 FT=516 IS=1 F'S=1 IT=516 FT=526 IS=1 FS=1 IT=526 FT=300 TT=0 TT=0 TT=220 FL=3231E IP=1025 FP=1025 FL=32316 FL=600 2IP=1025 FP=1025 IP=1205 2FP=1150 TP=0 TP=0 TP=0 I
| |
| TRAN CA=211 iS=1 FS=1 IT=300 FT=500 TT=1980. FL=600 IP=900 F2=1150 TP=0 TRAN TRAN TRAN CA=212 CA=213 CA=214 IS=1IFS=1 IT=500 FT=300 IS=1 FS=1 IT=300 FT=549 IS=1 FS=1 IT=526.FT=549 TT=180 TT=8964 TT=0 FL=600 I=1150 FP=690 FL=16158 IP=255 FP=1025 FL=32316 IP=1025 FP=1025 T 2=0 TP=0 TP=0 I
| |
| TRAN CA=215 IS=1 FS=1 IT=549 FT=375 TT=6264 FL=16158 IP=1025 FP=185 TP=0 TRAN TRAN TRAN CA=216 CA=217 CA=218 IS=1 FS=I IT=375 FT=330 1S31 FS=1 IT=330 FT=225 IS=1 FS=1 IT=225 FT=100 TT=600 TT=3780 TT=4500 FL=16158 IP=185 EL=16158 IP=105 FL=16158 IP=15 FP=105 FP=15 FP=15 T 2=0 TP=0 TP=0 I
| |
| TRAN CA=219 IS=1 FS=I IT=100 FT=100 TT=0 FL=2262 I=40 FP=1578 TP=0 TRAN TRAN TRAN CA=2 20 CA=221 CA=222 *IS=1 FS=I IT=526 FT=130 TT=0 FL=32316 IP=1025 FP=102 5 TP=0 I
| |
| TRAN CA=223 IS=1 FS=1 IT=130 FT=526 TT=0 FL=32316 IP=1025 FP=1025 TP=0 TRAN CA=224 CA=225 IS=1 FS=1IT=526 FT=375 IS=1 FS=1 IT=375 FT=100 TT=600 TT=9900 FL=32316 IP=1025 FL=32316 IP=215 FP=215 2P=15 TP=0 I
| |
| PAIR CA=201 CO=8.3 DI=0. 140 EX=8.5 *Tavg=85.0 PAIR CA=202 CO=8.3 FAIR CA=203 CO=9.4 PAIR DI=0. 140
| |
| )I=0. 151 CA=204 CO=10.5 DI=0. 162 EX=8.5 *Tavg=100.0 EX=8.5 *Tavg=324.5 EX=8.5 *Tavg=545.5 I
| |
| FAIR CA=205 CO=10.4 DI=0. 161 EX=8.5 *Tavg=534.0 PAIR PAIR PAIR CA=206 CO=10.4 CA=207 CO=10.4 DI=0.161 DI=0.161 CA=208 CO=10..3 DI=0. 161 EX=8.5 *Tavg=534.0 EX=8;5 *Tavg=534.0 EX=8.5 *Tavg=521..0 I
| |
| PAIR CA=209 CO=10.3 DI=0. 161 EX=8.5 *Tavg=521.0 PAIR PAIR CA=210 CO=9.9 PAIR CA=211 CO=9.8 CAe212 CO=9.8 DI=0.156 DI=0.155 DI=0.155 EX=8.5 *Tavg=413.0 EX=8.5 *Tavg=400.0 EX=8.5 *Tavg=400.0 I
| |
| PAIR CA=213 C0=9.9 DI=0.156 EX=8.5 *Tavg=424.5 PAIR PAIR CA=214 CO=10.4 DI=0.162 PAIR *CA=215 CO=10.0 DI=0.158
| |
| *CA=216 CO=9.5 DI=0.152 EX=8.5 *Tavg=537.5 EX=8.5 *Tavg=462.0 EX=8.5 *Tavg=352.5 I
| |
| PAIR CA=217 CO=9.2 DI=0.149 EX=8.5 *Tavg=277.5 PAIR CA=218 CO=8.7 PAIR
| |
| *PAIR CA=219 CO=8.3 CA=220 CO=9.0 DI=0.143 DI=0.140 DI=0.146 EX=8.5 *Tavg=162.5 EX=8.5 *Tavg=100.0 EX=8.5 *Tavg=225.0 I
| |
| File No.: VY-16Q-307 Revision: 0 Page A38 of A51 I F0306-0I RO I
| |
| | |
| 1 StructuralIntegrity Associates, Inc.
| |
| * PAIR CA=221 C0=9.0 DI=0.146 EX=8.5 *Tavg=225.0
| |
| *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 Reg3.inp
| |
| *---------------------------------------
| |
| *.BEGIN REGION 3 TRANSIENT CARDS & GEOMETRY FROM PUMP DISCHARGE TO HEADER
| |
| -------------------------------
| |
| OPER CA=1 TE=100 PR=1100 OPER CA=2 TE=100 PR=50 OPER CA=3 TE=549 PR=1035 OPER CA=4 TE=542 PR=1035 OPER CA=5, TE=526 PR=1035 OPER.CA=6 TE=542 PR=1035 OPER CA=7 TE=526 PR=1035 OPER CA=8 TE=516 PR=1035 OPER CA=9 TE=526 PR=1035 OPER CA=10 TE=300 PR=1160 OPER CA=11 TE=500 PR=1160 OPER CA=12 T.E=300 PR=700 OPER CA=13 TE=549 PR=1035 OPER CA=14 TE=549 PR=1035 OPER CA=15 TE=375 PR=195 OPER CA=16 TE=330 PR=115 OPER CA=17 TE=225 PR=25 OPER CA=18 TE=100 PR=25 OPER CA=19 TE=100 PR=1563 OPER CA=20 TE=225 PR=25 OPER CA=21 TE=225 PR=25 OPER CA=22 TE=130 PR=1035 OPER CA=23 TE=526 PR=1035 OPER CA=24 TE=375 PR=225 OPER CA=25 TE=100 PR=25 TRAN CA=201 IS=1 FS=1 IT=70 FT=100 TT=1800 FL=22 62 IP=15 FP=1115 TP=0 TRAN CA=202 IS=1 FS=1 IT=7 0 FT=1 00 TT=1800 FL=2262 IP=1115 FP= 65 TP=0 TRAN CA=203 IS=1 FS=1 IT=1 00 FT=54 9 TT=16164 FL=1615 8 IP=65. FP=1050 TP=0 TPAN CA=204 IS=1 FS=1 IT=549 FT=542 TT=0 FL=3231E *IP=105CI. FP=1050 TP=0 TRAN CA=205 IS=1 FS=1 IT=5 42 FT=526 TT=0 FL=3231( IP=105C IFP- 1050 TP=0 TRAN CA=206 FS=1 IT=526 FT=542 TT=900 FL=3231E IP=1050 FP=1050 TP=0 TRAN *CA=207 IS=1 FS=1 IT=542 FT=526 TT=360 FL=3231( IP=1050 FP=1050 TP=0 TRAN CA=208 IS=1 FS=1 IT=526 FT=516 TT=0 FL=3231E IP=1050 FP=1050 TP=0 TRAN CA=209 FS=1 IT=516 FT=526 TT=0 FL=3231E IP=1050 FP=1050 TP=0 TRAN CA=210 IS=1 FS=1 IT=526 FT=300 TT=220 FL=600 IP=1230 FP=1175 TP=0 TRAN CA=211 IS=1 FS=1 IT=300 FT=500 TT=1980 FL=600 IP=925 FP=1175 TP=0 TRAN CA=212 IS=1 FS=1 IT=500 FT=300 TT=180 FL=600 IP=1175 FP=715 TP=0 TRAN CA=213 IS=1 FS=1 IT=300 FT=549 TT=8964 FL=16158 IP=280 FP=1050 TP=0 TRAN CA=214 IS=1 FS1 IT=526 FT=549 TT=0 FL=32316 IP=1050 FP=1050 TP=0 TRAN CA=215 IS=1 FS=1 IT=549 FT=375 TT=6264 FL=16158 IP=1050 FP=210 TP=0 TRAN CA=216 IS=1 FS=1 IT=375 FT=330 TT=600 FL=16158 IP=210 FP=130 TP=0 TRAN CA=217 IS=1 FS=1 IT=330 FT=225 TT=3780 FL=16158 IP=130 FP=40 TP=0 TRAN CA=218 IS=1 FS=1 IT=225 FT=100 TT=4500 FL=16158 IP=40 FP=40 TP=0 TRAN CA=219 IS=1 FS=1 IT=100 FT=100 TT=0 FL=2262 IP=40 FP=1578 TP=0 TRAN CA=220 TRAN CA=221 TRAN CA=222 *ISl FS=1 IT=526 FT=130 TT=0 FL=32316 IP=1050 FP=1050 TP=0 TRAN CA=223 IS=1 FS=1 IT=130 FT=526 TT=0 FL=32316 IP=1050 FP=1050 TP=0 File No.: VY-16Q-307 Page A39 of A51 Revision: 0 F0306-01 RO
| |
| | |
| StructuralIntegrityAssociates, 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 PAIR PAIR CA=203 CO=9.4 DI=0.151 EX=8.5 *Tavg=324.5 CA=204 CO=10.5 DI=0.162 EX=8.5 *Tavg=545.5 CA=205 CO=10.4 DI=0.161 EX=8.5 *Tavg=534.0 I
| |
| 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
| |
| *PAIR CA=220 CO=9.0 DI=0.146 EX=8.5 *Tavg=225.0
| |
| *PAIR CA=221 CO=9.0 DI=0.146 EX=8.5 *Tavg=225.0
| |
| *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 CAý224 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 Reg3B.inp
| |
| -------------------------------
| |
| *BEGIN REGION 3B TRANSIENT CARDS & GEOMETRY AFFECTED BY RHR INITIATION
| |
| *k-------------------------------
| |
| "OPER CA=20 TE=225 PR=25 OPER CA=21 TE=180 PR=25 TRAM CA=220 IS=1 FS=1 IT=180 FT=225 TT=60 FL=22858 IP=40 FP*40 TRAN .CA=221 IS=1 FS=1 IT=225 FT=180 TT=60 FL=22858 IP=40 FP=40 PAIR CA=220 CO=8.8 1=T0.145 EX=8.5 *Tavg=2202..5 PAIR CA=220 C0=8.8 D1=0.145 EX=8.5 *Tavg=202.5 Reg4.inp
| |
| * ------------------------------
| |
| *BEGIN REGION 4 TRANSIENT CARDS & GEOMETRY'HEADER TO NOZZLE NODE 366
| |
| --------------------- *1 I----------
| |
| OPER CA=1 TE=100 PR=1100 OPER CA=2 TE=100 PR=50 OPER CA=3 TE=549 PR=1035 OPER CA=4 TE=542 PR=1035 OPER CA=5 TE=526 PR=1035 OPER CA=6 TE=542 PR=1035' OPER CA=7 TE=526 PRý1035 OPER CA=8 TE=516 PR=1035 OPER CA=9 TE=526 PR=1035 OPER CA=10 TE=300 PR=1160 OPER CA=11 TE=500 PR=1160 OPER CA=12 TE=300 PR=700 OPER CA=13 TE=549 PR=1035 File No.: VY-16Q-307 Page A40 of A51 Revision: 0 F0306-O1 RO I
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| | |
| V StructuralIntegrityAssociates, Inc.
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| I OPER CA=14 T E=549 PR=1035 OPER CA=15 T'E=375 PR=195 OPER CA=16 TE=330 PR=115 OPER CA=17 TE=225 PR=25 OPER CA=18 T E=100 PR=25 OPER CA=19 " T E=100 PR=1563
| |
| .OPER CA=20 T E=225 PR=25 OPER CA=21 T E=180 PR=25 OPER CA=22 T E=130 PR=1035 OPER CA=23 T E=526 PR=1035 OPER CA=24 T E=375 PR=225 OPER CA=25 TE=100 PR=25 TRAN CA=201 IS=1 F'S=1 IT=70 F'T=100 TT=1800 FL=905 IP=15" FP=1115 TP=0 TRAN CA=202 IS=1 F 3S=1 IT=100 F'T=100 TT=1800 FL=905 IP=1115 FP=65 TP=0 TRAN CA=203 IS=1 E'S=1 IT=100 F'T=549 TT=16164 FL=6463 IP=65 FP=1050 TP=0 TRAN CA=204 IS=1 FS=1 IT=549 FT=542 TT=0 FL=12926 IP=1050 FP=1050 TP=0 TRAN TRAN CA=205 IS=1 FS=1 IT=54 2 FT=526 TT=0 FL=12926 IP=i050 FP=1050 TP=0 CA=206 IS=1 FS=1 IT=-526 FT=542 TT=900 FL=12926 IP=1050 FP=1050 TP=0 TRAN TRAN CA=207 IS=1 FS=1 IT=542 FT=526 TT=360 FL=12926 IP=1050 FP=1050 TP=0 TRAN CA=208 IS=1 FS=1 IT=-52 6 FT=516 TT=0 FL=12926 IP=1050 FP=1050 TP=O TRAN CA=209 IS=1 FS=1 IT=516 FT=526 TT=0 FL=12926 IP=1050 FP=1050 TP=0 CA=210 IS=1 FS=1 IT=52 6 FT=300 TT=220 FL=400 IP=1230 FP=1175 TP=0 TRAN CA=211 IS=1 FS=1 IT=300 FT=500 TT=1980 FL=400 IP=925 FP=1175 TP=0 TRAN CA=212 IS=1 FS=1 IT=500 FT=300 TT=180 FL=400 IP1=175 FP=715 TP=0 TRAN CA=213 IS=1 FS=I IT=300 FT=549 TT=8964 FL=6463 IP=280 FP=1050 TP=0 TRAN CA=214 IS=1 FS=1 IT=526 FT=549 TT=0 FL=12926 IP=1050 FP=1050 TP=0 TRAN CA=215 IS=1 FS=1 IT=549 FT=375 TT=6264 FL=6463 IP=1050 FP=210 TP=0 TRAN CA=216 IS=1 FS-=1 IT=375 FT=330 TT=600 FL=6463 IP=210 FP=130 TP=0 TRAN CA=217 IS=1 FS=1 IT=330 FT=225 TT=3780 FL=6463 IP=130 FP=40 TP=0 TRAN CA=218 IS=1 FS=1 IT=225 FT=100 TT=4500 FL=9143 IP=40 FP=40 TP=0 TRAN
| |
| *CA=219 IS=1 FS=1 IT=100 FT=100 TT=0 FL=905 IP=40 FP=15.78 TP=0
| |
| *TRAN CA=220 IS=1 FS3=I IT=180 FT=225 TT=60 FL=9143 IP=40 FP=40 TP=0 TRAN CA=221 IS=1 FS=1 IT=225 FT=180 TT=60 FL=9143 IP=40 FP=40 TP=0 TRAN
| |
| *CA=222 IS=1 FS=1 IT=526 FT=130 TT=0 FL=12926 IP=1050 FP=1050 TP=0 TRAN CA=223 IS=1 FS=1 IT=130 FT=526 TT=0 FL=12926 IP=1050 FP=1050 TP=0 TRAN CA=224 IS=1 FS=1 IT=526 FT=375 TT=600 FL=12926 IP=1050 FP=240 TP=0 TRAN CA=225 IS=1 FS=1 IT=375 FT=100 TT=9900 FL=12926 IP=240 FP=40 . TP=0 PAIR CA=201 CO=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 *TavgS545.5 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 CO=10.4 DI=0.161 EX=8. 5 *Tavg=534.0 PAIR CA=208 CO=10.3 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=400.0 PAIR CA=213 CO=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 PAIR CA=220 CO=8.8 DI=0.145 EX=8.5 *Tavg=202.5 PAIR CA=221 CO=8.8 DI=0.145 EX=8.5 *Tavg=202.5 File No.: VY-16Q-307 Page A41 of A51 Revision: 0 F0306-OI RO
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| | |
| V StructuralIntegrityAssociates, Inc.
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| I I
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| *PAIR PAIR CA=223 CO=9.4 CA=222 CO=9.4 DI=0.151 EX=8.5 *Tavg=328.0 DI=0.151 EX=8.5 *Tavg=328.0 PAIR CA=224 CO=10.0 DI=0.157 EX=8.5 *Tavg=450.5 I
| |
| PAIR CA=225 CO=9.0 DI=0.147 EX=8.5 *Tavg=237.5 ReO5.inp
| |
| *--B -------------------------------------
| |
| I
| |
| *BEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLENODE
| |
| -------------------------------
| |
| OPER CA=1 TE=100 PR=1100 336 I
| |
| CA=2 I
| |
| OPER TE=I00 PR=50 OPER CA=3 TE=549 PR=1035 QPER CA=4 TE=542 PR=1035 OPER CA=5 TE=526 PR=1035 OPER I
| |
| CA=6 TE=542 PR=1035 OPER CA=7 TE=526 PR=1035 OPER CA=8 TE=516 PR=1035 OPER CA= 9 TE=526 PR=1035 I
| |
| OPER CA=10 TE=300 PR=1160 OPER CA=11 TE=500 PR=1160 OPER CA=12 TE=300 PR=700 OPER CA= 13 TE=549 PR=1035 I
| |
| OPER CA=14 TE=549 PR=1035 OPER CA=15 TE=375 PR=195 OPER CA=16 TE=330 PR=115 OPER CA=17 TE=225 PR=25 I
| |
| OPER CA=18 TE=100 PR=25 OPER CA=1 9 TE=100 PR=1563 OPER CA=20 TE=225 PR=25 OPER CA=21 TE=180 PR=25 I
| |
| OPER CA=22 TE=130 PR=1035 OPER CA=23 TE=526 PR=1035 OPER CA=24 TE=375 PR=225 OPER CA=25 TE=100 PR=25 TRAN CA=201 IS=1 F S=1 IT=70 FT=100 TT=1800 FL=452 IP=15 FP=1115 TP=0 TRAN TRAN TRAN CA=202 IS=1 F S=1 IT=100 FT=I 00 CA=2O3 IS=1 F S=1 IT=100 FT=54 9 TT=1800 TT=16164 FL=452 FL=3232 IP=1115 FP=65 IP=65 TP=0 FP=1050,TP=0 I
| |
| TRAN TRAN TRAN CA=20 4 IS=1 FS= I -IT=549 CA=20 5 IS=1 FS=J IT=542 FT=526 CA=20 '6 IS=1 FS=1 -IT=526 CA=20 '7 IS=1 FS=.l IT=542 FT=526 FT=542 FT=542 TT=0 TT=0 TT=900 FL=6463. IP=1050 FP=1050 TP=0 FL=6463 FL=6463 FL=6463 IP=1050 FP=105.0 TP=0 IP=1050 FP=1050 TP=0 IP=1050 FP=1050 TP=0 I
| |
| TRAN TT=360 TRAN TRAN TRAN CA=20 '8 IS=1 FS= 1 IT=52 6 FT=516 CA=20 '9 IS=1 FS=1 *IT=516 FT=526 CA=21 0 IS=1 FS=1 *IT=526 FT=300 TT=0.
| |
| TT=0 TT=220 FL=6463 FL=6463 FL=200 IP=1050 FP=1050 TP=0 IP=1050 FP=1050 TP=0 IP=1230 FP=1175 TP=0 I
| |
| CA=211 IS=1 FS=1 IT=300 FT=500 TT=1980 FL=200 IP=925 .FP=1175 TP=0 TRAN TRAN TRAN TRAN 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 TT=180 TT=8964 TT=0 FL=200 FL=3232 FL=6463 IP=1175 FP=715 IP=280 TP=0 FP=1050 TP=0 IP=1050 FP=1050 TP=0 I
| |
| CA=215 IS=1 FS=1 IT=549 FT=375 TT=6264 FL=3232 IP=1050 FP=210 TP=0 TRAN TRAN TRAN TRAN 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 TT=600 TT=3780 TT=4500 FL=3232 FL=3232 FL=4571 IP=210 IP=130 IP=40 FP=130 TP=0 FP=40 FP=40 TP=0 TP=0 I
| |
| CA=219 IS=1 FS=1. IT=100 FT=100 TT=0 FL=452 IP=40 F.P=1578 TP=0 TRAN TRAN TRAN TRAN CA=220 IS=1 FS='1 IT=180 FT=225 CA=221 IS=1 FS=1 IT=225 FT=180
| |
| *CA=222 IS=1 FS=1 IT=526 FT=130 TT=60 TT=60 TT=0 FL=4572 FL=4572 FL=6463 IP=40 IP=40 FP=40 FP=40 TP=0 TP=0 IP=1050 FP=1050 TP=0 I
| |
| CA=223 IS=1 FS=1 IT=130 FT=526 TT=0 FL=6463 IP=1050 FP=1050 .TP=0 TRAN File No.: VY-16Q-307 CA=224 IS=1 FS=1 IT=526 FT=375 TT=600 FL=6463 IP=1050 FP=240 TP=0 Page A42 of A51 I
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| Revision: 0 F0306-01 RO I
| |
| | |
| U Structural IntegrityAssociates, Inc.
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| TRAN CA=225 IS=1 FS=1 IT=375 FT=100 TT=9900 FL=6463 IP=240 FP=40 TP=0 PAIR CA=201 CO=8.3 DI=0.140 EX=8.5 *Tavg=85.0 PAIR CA=202 CO8.3 DI=0. 140 EX=8.5 *Tavg100.0 PAIR CA=203 CO=9.44 DI=0. 151 EX=8.5 *Tavg=324.5 PAIR CA=204 CO=10.5 DI=0. 162 EX=8.5 *Tavg=545.5
| |
| *PAIR CA=205 CO=10. 4 DI=0.163 EX=8.5. *Tavg=534.0 PAIR CA=206 CO= 10.4 DI=0. 161 EX=8.5 *Tavg=534.0 PAIR CA=207 CO=10.4 DI=0. 161 EX=8.5 *Tavg=534.0 PAIR CA=208 CO=10.3 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. 15i EX=8.5 *Tavg=413.0 PAIR CA=211 CO=9.8 DI=0. 155 i EX=8.5 *Tavg=400.0 PAIR CA=212 CO=9.8 D1=0. 155 5 EX=8.5 *Tavg=400.0 PAIR CA=213 CO=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.O 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 PAIR CA=220 CO=8.8 DI=0.145 EX=8.5 *Tavg=202.5 PAIR CA=221 CO=8.8 DI=0.145 EX=8.5 *Tavg=202.5
| |
| *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 Reg6.inp
| |
| * ----------------------------------------
| |
| *BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO NOZZLE NODE 336
| |
| -------------------------------
| |
| OPER CA=1 TE=100 PR=1100 OPER CA=2 TE=100 PR=50 OPER CA=3 TE=549 PR=1035 OPER CA=4 TE=542 PR=1035 OPER CA=5 TE=526 PR=1035 OPER CA=6 TE=542 PR=1035 OPER CA=7 TE=526 PR=1035 OPER CA=8 TE=516 PR=1035 OPER CA=9 TE=526 PR=1035 OPER CA=10 TE=300 PR=1160 OPER CA=11 TE=500 PR=1160 OPER CA=12 TE=300 PR=700, OPER CA=13 TE=549 PR=1035 OPER CA=14 TE=549 PR=1035 OPER CA=15 TE=375 PR=195 OPER CA=16 TE=330 PR=115 OPER CA=17 TE=225 PR=25 OPER CA=18 TE=100 PR=25 OPER CA=19 TE=100 PR=1563 OPER CA=20 TE=225 PR=25 OPER CA=21 TE=180 PR=25 OPER CA=22 TE=130 PR=1035 OPER CA=23 TE=526 PR=1035 OPER CA=24 TE=375 PR=225 OPER CA=25 TE=100 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 Page.A43 of A51 Revision: 0 F0306-01 RO
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| V Structural IntegrityAssociates, Inc.
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| I TRAN TRAN
| |
| .TRAN CA=202 CA=2 03 CA=204 IS=1 FS=1 IT=100 FT=100 IS=1 FS=1 IT=100 FT=549 IS=1 FS=1 IT=549 FT=542 TT=1800 TT=16164 TT=0 FL=452 IP=1115 FP=65 FL=3232 IP=65 TP=0 FP=1050 TP=0 FL=6463 IP=1050 FP=1050 TP=0 I
| |
| TRAN CA=205 IS=1 FS=1 IT=542 FT=526 TT=0 FL=64 63 IP=1050 FP=1050 TP=0 TRAN TRAN TRAN CA=206 CA=207 CA=208 IS=1 FS=1 IT=526 FT=542, TT=900 IS=1 FS=1 IT=542 FT=526 IS=1 FS=I IT=526 FT=516 TT=360 TT=0 FL=6463 IP=1050 FP=1050 TP=0 FL=6463 IP=1050 FP=1050 TP=0 FL=6463 IP=1050 FP=1050 TP=0 I
| |
| TRAN CA=209 IS=1 FS=1 IT=516 FT=526 TT=0 FL=6463 IP=1050 FP=1050 TP=0 TRAN TRAN
| |
| . TRAN CA=210 CA=211 cA=212 IS=1 FS=1 IT=526 FT=300 IS=1 FS=1 IT=300 FT=500 IS=1 FS=1 IT=500 FT=300 TT=220 TT=1980 TT=180 FL=200 FL=200 FL=200 IP=1230 FP=1175 TP=0 IP=925 FP=1175 TP=0 IP=1175 FP=715 TP=0 I
| |
| TRAN CA=213 IS=1 FS=1 IT=300 FT=549 TT=8964 FL=3232 IP=280 FP=1050 TP=0 TRAN TRAN TRAN CA=214 CA=215 CA=216 IS=1 FS=1 IT=526 FT=549 IS=1 FS=1 IT=549 FT=375 IS=1 FS=1 IT=375 FT=330 TT=0 TT=6264 TT=600 FL=6463 IP=1050 FP=1050 TP=0 FL=3232 IP=1050 FP=210 FL=3232 IP=210 FP=130 TP=0 TP=0 I
| |
| TRAN CA=217 IS=1 FS=1 IT=330 FT=225 TT=3780 FL=3232" IP=130 FP=40 TP=0 TRAN TRAN TRAN CA=218 CA=219 CA=220 IS=1 FS=1 IT=225 FT=100 IS=1 FS=1 IT=100 FT=100 IS=1 FS=1 IT=i80 FT=225 TT=4500 TT=0 TT=60 FL=4572 IP=40 FL=452 IP=40 FL=4 572 IP=40 FP=40 TP=0.
| |
| FP=1578 TP=0 FP=40 TP=0 I
| |
| TRAN CA=221 IS=1 FS=1 IT=225 FT=180 TT=60 FL=4572 IP=40 FP=40 TP=0 TRAN TRAN TRAN CA=222 CA=223 CA=224 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=0 TT=0 TT=600 FL=6463 IP=1050 FP=1050 TP=0 FL=6463 IP=1050 FP=1050 TP=0 FL=6463 IP=1050 FP=240 TP=0 I
| |
| TRAN CA=225 IS=1 FS=1 IT=375 FT=100 TT=9900 FL=6463 IP=240 FP=40 TP=0 PAIR PAIR CA=201 CO=8. 3 DI=0.140 EX=8.5 CA=202 CO=8. 3 DI=0.140 EX=8.5
| |
| *Tavg=85.0
| |
| *Tavg=100.0 I
| |
| PAIR CAý203 CO=9. 4 DI=0.151 EX=8.5 *Tavg=324.5
| |
| . PAIR PAIR PAIR CA=204 CO=10.5 CA=205 CO=10.4 DI=0.162 EX=8. 5 *Tavg=545.5 DI=0. 161 EX=8. 5 *Tavg=534 .0 CA=206 C0=10.4 DI=0.161 EX=8. 5 *Tavg=534. 0 I
| |
| PAIR CA=207 CO=10.4 DI=0. 161 EX=8. 5 *Tavg=534 .0 PAIR PAIR PAIR CA=208 CO=10.3 DI=0.161 EX=8 .5 *Tavg=521. 0 CA=209 CO=10.3 DI=0.161 EX=8. 5 *Tavg=521. 0 CA=210 CO=9: 9 DI=0. 156 EX=8. 5 *Tavg=413.0 I
| |
| PAIR CA=211 CO=9.8 DI=0.155 EX=8.5 *Tavg=400.0 PAIR PAIR PAIR CA=212 CO=9.8 CA=213 CO=9.9 DI=0.155 EX=8:5 *Tavg=400.0 DI=0.156 EX=8.5 *Tavg=424.5 CA=214 CO=10.4 DI=0.162 EX=8.5 *Tavg=537.5 I
| |
| PAIR CA=215 CO=10.0 DI=0.158 EX=8.5 *Tavg=462.0 PAIR PAIR PAIR CA=216 CO=9.5 CA=217 CO=9.2 CA=218 CO=8.7 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 I
| |
| PAIR CA=219 CO=8.3 DI=0.140 EX=8.5 *Tavg=100.0 PAIR PAIR PAIR CA=220 CO=8.8 CA=221 CO=8.8 CA=222 CO=9.4 DI=0.145 EX=8.5 *Tavg=202.5 DI=0.145 EX=8.5 *Tavg=202.5 DI=0.151 EX=8.5' *Tavg=328.0 I
| |
| PAIR CA=223 C0=9.4 DI=0.151 EX=8.5 *Tavg:328.0 PAIR PAIR CA=224 CO=10.0 DI=0.157 EX=8.5 *Tavg=450.5 CA=225 CO=9.0 DI=0.147 EX=8.5 *Tavg=237.5 I Reg7A.inp
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| * ----------------------------------------
| |
| *BEGIN REGION 7A TRANSIENT CARDS & GEOMETRY TO RHR SUPPLY VALVE NODE 550 I
| |
| - - - - - - - - - - - - - - - - - - - - -
| |
| OPER CA=1 TE=100 PR=1100 I OPER CA=2 TE=100 PR=50 OPER CA=3 TE=549 PR=1010 OPER CA=4 File No.: VY-16Q-307 TE=542 PR=1010 Page A44 of A51 I
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| Revisionw 0 F0306-01 RO I
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| StructuralIntegrityAssociates, Inc.
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| I OPER CA=5 TE=526 PR=1010
| |
| *OPER CA=6 TE=542 PR=1010 OPER CA=7 TE=526 PR=1010 OPER CA=8 TE=516 PR=1010 OPER CA=9 TE=526 PR=1010 OPER CA=10 TE=300 PR=1135 OPER CA=11 TE=500 PR=1135 OPER CA=12 TE=306 .PR=675 OPER CA=13 TE=549 PR=1010 OPER CA=14 TE=549 PR=1010 OPER CA=15 TE=375 PR=170 OPER CA=16 TE=330 PR=90 OPER CA=17 TE=225 PR=0 OPER CA=18 TE=100 PR=0.
| |
| OPER CA=19 TE=100 PR=1563 OPER CA=20. TE=225 PR=0 OPER CA=21 TE=225 PR=0 OPER CA=22 TE=130 PR=1010 OPER CA=23 TE=526 PR=1010 OPER CA=24 TE=375 PR=200 OPER CA=25 TE=100 PR=0
| |
| *TRAN CA=201 IS=1 IT=70 FT=100 TT=1800 FL=143 IP=15 FP=1115 TP=0 FS=1 TRAN CA=202 IS=1 IT=100 FT=100 TT=1800 FL=143 IP=1115 FP=65 TP=0 TRAN CA=203 IS=1 .PS=1 IT=100 FT=54 9 TT=16164 FL=300 IP=65 FP=1025 TP=0 TRAN CA=204 IS=J - S=1i IT=549 FT=542 TT=0 FL=364 IP=I025 FP=1025 TP=0 TRAN CA=205 I S=] - P=1i IT=542 FT=526 TT=0 FL=358 IP=1025 FP=1025 TP=0 TRAN CA=206 FS=1i IT=526 FT=542 TT=900 FL=358 IP=1025 FP=1025 TP=0 TRAN CA=207 13=1 FS=1 IT=542 FT=526 TT=360 FL=358 IP=1025 FP=1025 TP=0 TRAN CA=208 I S=1 FS=1 IT=526 FT=516 TT=0 FL=351 IP=1025 FP=1025 TP=0 TRAN CA=209 IT=516 FT=526 TT=0 FL=351 IP=1025 FP=1025 TP=0 13=1 F3=1 TRAN CA=210 IT=526 FT=300 TT=220 FL=306 IP=1205 FP=1150 TP=0 TRAN CA=211 IS=1 FS=I IT=300 FT=500 TT=1980 FL=301 IP=900 FP=1150 TP=0 TT=180 TRAN CA=212 IS=1 FS=1 IT=500 FT=300 FL=301 IP=1150 FP=690 TP=0 TRAN CA=213 IS=1 FS=1 IT=300 FT=549 TT=8964 FL=310 IP=255 FP=1025 TP=0 TRAN CA=214 IS=l FS=I IT=526, FT=549 TT=0 FL=360 IP=1025 FP=1025 TP=0 TRAN CA=215 IS=1 FS=l IT=549 FT=375 TT=6264 FL=320 IP=1050 FP=185 TP=0 TRAN CA=2i 6 IS=I FS=IIT=375 FT=330 TT=600 FL=282 IP=185 FP=105 TP=0 TRAN CA=217 IS=1 FS=I IT=330 FT=225 TT=3780 FL=260 IP=105 FP=15 TP=0 TRAN CA=218 IS=1 FS=I IT=225 FT=100 TT=4500 FL=6700 IP=15 FP=15 TP=O TRAN CA=219 IS=1 FS=l IT=100 FT=100 TT=0 FL=158 IP=40 FP=1578 TP=0 TRAN CA=220 *IS=1 FS=i IT=225 FT=225 TT=60 FL=6700 IP=15 FP=15 TP=0 TRAN CA=221 *IS=I FS=1 IT=225 FT=225 TT=60 FL=6700 IP=15 FPP15 TP=0 TRAN CA=222 *IS=I FS=1 IT=526 FT=130 TT=0 FL=272 IP=1025 FP=1025 TP=0 TRAN CA=223 IS=1 FS=1 IT=130 FT=526 TT=0 FL=2 72 IP=1025 FP=1025 TP=0 TRAN CA=224 IS=1 FS=1 IT=526 FT=375 TT=600 FL=320 IP=1025 FP=215 TP=0 TRAN CA=225 IS=1 FS=I IT=375 FT=100 TT=9900 FL=234 IP=215 FP=15 TP=0 PAIR CA=201 CO=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. DI=0.163 EX=8.5 *Tavg=545.5 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 CO=l0. 4 DI=0. 161* EX=8.5 *Tavg=534.0 PAIR CA=208 C0=10.3
| |
| * 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 D1=0.155 EX=8.5 *Tavg=400.0 File No.: VY-16Q-307 Page A45 of A51 Revision: 0 F0306-OI RO
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| V StructuralintegrityAssociates, Inc.
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| I I
| |
| PAIR PAIR PAIR 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 CA=215 CO=10.0 DI=0.158 EX=8.5 *Tavg=462.0
| |
| )
| |
| I PAIR CA=216 C0=9.5 DI=0.152 EX=8.5 *Tavg=352.5 PAIR PAIR PAIR CA=217 CO=9.2 CA=218 CO=8.7 CA=219 CO=8.3 DI=0.149 EX=8.5 *Tavg=277.5 DI=0.143 EX=8.5 *Tavg=162.5 DI=0.140 EX=8.5 *Tavg=100.0 I
| |
| *PAIR CA=220 CO=9.0 DI=0.146 EX=8.5 *Tavg=225.0
| |
| *PAIR
| |
| *PAIR PAIR CA=221 C0=9.0 CA=222 CO=9.4 CA=223 CO=9.4 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 I
| |
| PAIR CA=224 CO=10.0 DI=0.157 EX=8.5 *Tavg=450.5 PAIR CA=225 CO=9.0 ReaTB.inp DI=0.147 EX=8.5 *Tavg=2.37.5 I
| |
| I
| |
| ------------------- I-------------
| |
| *BEGIN REGION 7B TRANSIENT CARDS & GEOMETRY FROM RHR-SUPPLY VALVE TO PENET. NODE 565
| |
| *---------------------------
| |
| CA=1 I
| |
| OPEF TE=100 PR=120 OPEF CA=2 TE=100 PR=50 OPER CA=3 TE=150 PR=120 OPER CA=4 TE=150 PR=120 OPER OPER OPER CA=5 CA=6 CA=7 CA=8 TE=150 TE=150 TE=150 TE=150 PR=120 PR=120 PR=120 PR=120 I
| |
| OPER CA=9 TE=150 PR=120 I
| |
| OPER OPER CA=10 TE=150 PR=120 OPER CA=1 1 TE=150 PR=120 OPER CA=f12 TE=150 PR=120 OPER CA=13 TE=150 PR=120 OPER OPER OPER CA=14 CA=15 CA=16 TE=150 TE=150 TE=150 PR=120 PR=120 PR=120 I
| |
| TE=150 PR=100 OPER I
| |
| CA=17 OPER CA=1 8 TE=100 PR=0 OPER CA=1 9 TE=100 PR=4 50 OPER CA=2 0 TE=225 PR=25 OPER OPER OPER CA=21 CA=22 CA=23 CA=2 4 TE=150 TE=150 TE=150 TE=150 PR=25 PR=100 PR=1035 PR=100 I
| |
| OPER OPER CA=25 TRAN TE=150 CA=201 IS=1 FS=1 IT=70 PR=100 FT=100 TT=1800 FL=143 IP=15 FP=135 TP=0 I
| |
| TRAN CA=202 IS=1 FS=1 IT=100 FT=100 TT=1800 FL=143 IP=135 FP=65 TP=0 TRAN TRAN TRAN CA=203 IS=1 FS=1 IT=100 CA=204 CA=205 FT=150 TT=16164 FL=300 IP=65 FP=135 TP=0 I
| |
| TRAN CA=206 TRAN TRAN TRAN CA=2.07 CA=208 CA=209 I
| |
| TRAN CA=210 TRAN TRAN TRAN CA=211 CA=212 CA=213 I
| |
| TRAN CA=214 TRAN CA=215 File No.: VY-16Q-307 Page A46 of A51 I
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| Revision: 0 F0306-01 RO I
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| V Structuralintegrity Associates, Inc.
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| TRAN CA=2 16 TRAN CA=217 TRAN CA=218 IS=1 FS=I IT=225 FT=100 TT=4500 FL=6700 IP=15 FP=15 TP=0 TRAN CA=219 IS=1 FS=1 IT=100 FT=100 TT=0 FL=143 IP=15 FP=465 TP=0 TRAN CA=220 IS=1 FS=1 IT=150 FT=225 TT=60 FL=6700 IP=40 FP=40 TP=0 TRAN CA=221 *IS=1 FS=1 IT=150 FT=150 TT=0 FL=6700 IP=40 FP=40 TP=0 TRAN CA=222 TRAN CA=223 TRAN CA=224 TRAN CA=225 PAIR CA=201 CO=2 7.6 DI=0. 529 EX=6.4 *Tavg8 5.0 PAIR *Tavg=100.0 CA=202 CO=27 .6 DI=0. 512 EX=6.4 PAIR
| |
| *PAIR CA=203 CO=27.6 DI=0. 506 EX=6.4 *Tavg=125.0 CA=204 CO=27.6 DI=0.49S EX=6.4 *Tavg=150.0
| |
| *PAIR CA=205 CO=2 7.6 DI=0.49£ EX=6.4 *Tavg=150.0
| |
| *PAIR *Tavg=150.0 CA=206 CO=27 .6 DI=0.49S EX=6.4
| |
| *PAIR *Tavg=150.0
| |
| *PAIR CA=207 CO=27. 6 DI=0. 49S EX=6.4
| |
| *PAIR CA=208 CO=27.6 DI=0. 49SI EX=6.. 4 *Tavg=150.0
| |
| * PAIR CA=209 CO=27 .6 DI=0.49SI EX=6.4 *Tavg=i50.0 CA=210 CO=27.6 DI=0.499 EX=6.4 *Tavg=150.0
| |
| *PAIR
| |
| *PAIR CA=211 CO=27 .6 DI=0. 499 P EX=6.4 *Tavg=150.0
| |
| *PAIR CA=212 CO=27.6 DI=0. 499 EX=6.4 *Tavg=150.0
| |
| *PAIR CA=213 CO=27. 6 DI=0.499 EX=6.4 **Tavg=150.0 CA=214 CO=27.6 I=0. 499 EX=6.4 .*Tavg=150.0
| |
| * PAIR
| |
| *PAIR CA=215 CO=27.6 DI=0.499 EX=6. 4 *Tavg=150.0 CA=216 CO=27 .6 DI=0.499 EX=6. 4 *Tavg-1.50.0
| |
| *PAIR CA=217 CO=27. 6 DI=0.499 EX=6.4 *Tavg=150.0 PAIR CA=218 CO=27.6 DI=0.496 EX=6.4 *Tavg=162.5 PAIR CA=219 CO=27.6 DI=0. 512 EX=6.. 4 *Tavg=100.0 PAIR CA=220 CO=27. 6 DI=0.489 EX=6. 4 *Tavg=187.5 PAIR
| |
| *PAIR CA=221 CO=27.6 DI=0.499 EX=6. 4 *Tavg=l50.0 CA=222 CO=27. 6 DI=0.499 EX=6. 4 *Tavq=150.0
| |
| *PAIR *Tavg=150.0 CA=223 CO=27.6 DI=0.499 EX=6.4
| |
| *PAIR CA=224 CO=27. 6 DI=0.499 EX=6. 4 *Tavg=150.0
| |
| *PAIR CA=225 CO=27. 6 DI=0.499 EX=6. 4 *Tavg=150.0 Reg8.inp
| |
| *---------------------------------------
| |
| *BEGIN REGION 8 TRANSIENT CARDS & GEOMETRY FOR 4 INCH BYPASS OPER CA= I TE=100 PR=110.0 OPER CA=2 TE=100 PR=50 OPER CA=3 TE=549 PR=1035 OPER CA= 4 TE=542 PR=1035 OPER CA=5 TE=526 PR=1035 OPER CA= 6 TE=542 PR=1035 OPER CA=7, TE=526 PR=1035 OPER CA= 8 TE=516 PR=1035 OPER CA= 9 TE=526 PR=1035 OPER CA=10 TE=300 PR=1160 OPER CA=11 TE=500 PR=1160 OPER CA=12 TE=300 PR=700 OPER CA=13 TE=549 PR=1035 OPER CA=14 TE=549 PR=1035 OPER OPER CA=15 TE=375 PR=195 CA=16 TE=330 PR=115 OPER CA= 17. TE=225. PR=25 OPER CA=18 TE=100 PR=25 File No.: VY-16Q-307 Page A47 of A51 Revision: 0 F0306-01 RO
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| | |
| StructuralIntegrityAssociates, Inc.
| |
| I I
| |
| OPER CA=1 9 OPER CA=20 OPER CA=21 TE=100 TE=225 TE=225 PR=1563 PR=25 PR=25 I
| |
| OPER CA=22 TE=130 PR=1035 OPER CA=2 3.
| |
| OPER CA=24 OPER CA=25 TE=526 TE=375 TE=100 PR=1035 PR=225 PR=25 I
| |
| TRAN TRAN TRAN CA=201 IS=i FS=1 IT=70 FT=100 TT=1800 CA=202 IS=1 FS=1 IT=100 FT=100. TT=1800 CA=203 IS=1 FS=I IT=100 FT=549 TT=16164 FL=23.5 FL=23.5 FL=168 IP=15 FP=1115 TP=0 IP=1115 FP=65 IP=65 TP=0 FP=1050 TP=0 I
| |
| TRAN CA=204 IS=]L FS=1 IT=549 FT=542 TT=0 FL=335 IP=1050 FP=1050 TP=0 TRAN TRAN TRAN CA=205 IS=]- FS=1 IT=542 FT=526 0v=2 06 IS=]1 FS=1 IT=526 FT=542 CA=207 IS=] - FS=1 IT=542 FT=526 TT=0 TT=900.
| |
| TT=360 FL=335 FL=335 FL=335 IP=1050 FP=1050 TP=0 IP=1050 FP=1050 TP=0 IP=1050 FP=1050 TP=0 I
| |
| TRAN CA=268 IS=] FS=l IT=526 FT=516 TT=0 FL=335 IP=1050 FP=1050 TP=0 TRA1 TRAN TRAN OA=209 IS=] FS=1 IT=516 FT=526 CA=2,10 IS=2
| |
| * FS=1 IT=526 FT=300 CA=211 IS=1 FS=1 IT=300 FT=500 TT=0 TT=220 TT=1980 FL=335 FL=6 FL=6 IP=1050 FP=1050 TP=0 IP=1230 FP=1175 TP=0 IP=925 FP=1175 TP=0 I
| |
| TRAN CA=212 IS=_1 FS=1 IT=500 FT=300 TT=180 FL=6 IP=1175 FP=715 TP=0 TRAN CA=213 IS=1 FS=1 IT=300 FT=549 TT=8964 FL=167.5 IP=280 FP=1050 TP=0 TRAN TRAN TRAN 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 TT=0 TT=6264 TT=600 FL=335 FL=167.5 FL=167.5 IP=1050 FP=1050 TP=0 IP=1050 FP=210 TP=0 IP=210 FP=130 TP=0 I
| |
| TRAN TRAN TRAN 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 TT=3780 TT=4500 TT=0 FL=167.5 FL=167.5 FL=23.5 IP=130 IP=40 IP=40 FP=40 FP=40 TP=0 TP=0 FP=1578 TP=0 I
| |
| TRAN CA=220 TRAN TRAN TRAN CA=221 CA=222 *IS=I FS=1 IT=526 FT=130 CA=223 IS=1 FS=1 IT=130 FT=526 TT=0 TT=0 FL=335 IP=105C FP=1050 TP=0 FL=335 IP=1050 FP=1050 TP=0 I
| |
| TRAN CA=224 IS=1 FS=1 IT=526 FT=375 TT=600 FL=335 IP=1050 FP=240 TP=0 TRAN CA=225 IS=1 FS=1 IT=375 FT=100 TT=9900 PAIR CA=201 CO=8. 3 DI=0. 140 EX=8.5 *Tavg=85.0 FL=335 IP=240 FP=40 TP=0 I
| |
| 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 PAIR CA=204 CO=10.5 DI=0. 162 EX=8.5 *Tavg=545.5 CA=205 CO=10.4 DI=0.161 EX=8.5 *Tavg=534.0 I
| |
| PAIR CA=206 CO=10.4 DI=0.161 EX=8.5 *Tavg=534 .0 PAIR PAIR PAIR CA=207 CO=10..4 Di=0. 161 EX=8.5 *Tavg=534.0 CA=208 CO=10.3 DI=0.161 EX=8.5 *Tavg=521.0 CA=209 C0=10.3 DI=0.161 EX=8.5 *Tavg=521.0 I
| |
| PAIR CA=2 10 C0=9. 9 DI=0.156 EX=8.5 *Tavg=413.0 PAIR CA=211 CO=9.8 PAIR CA=212 CO=9.8 PAIR CA=213 CO=9.9 DI=0.155 EX=8.5 *Tavg=400.0 DI=0.155 EX=8.5 *Tavg=400.0 DI=0.156 EX=8.5 *Tavg=424.5 I
| |
| 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 C0=9.5 PAIR CA=217 CO=9.2 DI=0.152 EX=8.5 *Tavg=352.5 DI=0.149 EX=8.5 *Tavg=277.5 I
| |
| PAIR CA=218 CO=8.7 DI=0.143 EX=8.5 *Tavg=162.5 PAIR CA=219 CO=8.3
| |
| *PAIR CA=220 C0=9.0
| |
| *PAIR CA=221 CO=9.0 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 I
| |
| *PAIR CA=222 C0=9.4 DI=0.151 EX=8.5 *Tavg=328.0 PAIR PAIR CA=223 CO=9.4 CA=224 CO=10.0 DI=0.151 EX=8.5 *Tavg=328.0 DI=0.157 EX=8.5 *Tavg=450.5 I1 PAIR CA=225 CO=9.0 DI=0.147 EX=8.5 *Tavg=237.5 File No.: VY-16Q-307 Revision: 0 Page A48 of A51 U F0306-01 RO I
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| V StructuralIntegrity Associates, Inc.
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| Reg9A.inp
| |
| * ------------------- - --- - -- - -- - - -- ------
| |
| *BEG1ýN REGITON 9A TRANSIENT CARDS K GEOMETRY FOR RHR RETURN FROM TEE TO VALVE NODE 660 OPER CA=1 TE=100 PR=1100 OPER CA=2 TE=100 PR=50 OPER CA=3 TE=549 PR=1035 OPER CA=4 TE=542 PR=1035 OPER CA=5 TE=526 PR=1035 OPER CA=6 TE=542 PR=1035 OPER CA=7 TE=526 PR=1035 OPER CA=8 TE=516 PR=1035 OPER CA=9 TE=526 PR=1035 OPER CA=10 TE=300 PR=1160 OPER CA=11 TE=500 PR=1160 OPER CA=12 TE=300 PR=700 OPER CA=13 TE=54 9 PR=1035 OPER CA=14 TE=54.9 PR=1035 OPER CA=15 TE=375 PR=195.
| |
| OPER CA=16 TE=330 PR=115 OPER CA=17 TE=225 PR=25 OPER CA=18 TE=100 PR=100 OPER CA=19 TE=100 PR=1563 OPER CA=20 TE=225 PR=25 OPER CA=21 TE=70 PR=25 OPER CA=22 TE=130 PR=1035 OPER CA=23 TE=526 PR=1035 OPER CA=24 TE=375 PR=225 OPER CA=25 TE=100 PR=25 TRAN CA=201 IS=1 FS=1 IT=70 FT=100 TT=1800 FL=204 IP=15 FP=1115 TP=0 TRAN CA=202 IS=1 FS=1 IT=100 FT=100 TT=1800 FL=204 IP=1115 FP=65 TP=0 TRAN CA=203 IS=1 FS=1 IT=100 FT=549 TT=16164 FL=247 IP=65 FP=1050 TP=0 TRAN CA=204 IS=1 FS=1 *IT=549 FT=542 TT=0 FL=520 IP=1050 FP=1050 TP=0 TRAN CA=205 IS=1 FS=I IT1=542 FT=526 TT=0 FL=511 IP=1050 FP=1050 TP=0 TRAN CA=206 IS=1 FS=1 IT1=52 6 FT=542 TT=900 FL=511 IP=1050 FP=1050 TP=0 TRAN CA=207 IS=l FS=1 11=542 FT=526 TT=360 FL=511 IP=1050 FP=1050 TP=0 Is=1 TRAN CA=208 FS=1 11T=526 FT=516 TT=0 FL=502 IP=1050 FP=1050 TP=0 TRAN CA=209 IS=1 FS=1 11=516 FT=526 TT=0 FL=502 IP=1050 FP=1050 TP=0 TRAN CA=210 1S=I FS=1 IT=526 FT=300 TT=220 FL=437 IP=1230 FP=1175 TP=0 TRAN CA=211 IS=1 FS=1 IT=300 FT=500 TT=1980 FL=429 IP=925 FP=1175 TP=0 TRAN CA=212 IS=1 FS=1 IT=500 FT=300 TT=180 FL=429 IP=1175 FP=715 TP=0 TRAN CA=213 IS=1 FS=1 IT=300 FT=549 TT=8964 FL=443 IP=280 FP=1050 TP=0 TRAN CA=214 IS=1 FS=1 IT=526 FT=549 TT=0 FL=514 IP=1050 FP=1050 TP=0 TRAN CA=215 IS=1 FS=1 IT=549 FT=375 TT=6264 FL=458 IP=1050 FP=210 TP=0 TRAN CA=216 IS=1 FS=1 IT=375 FT=330 TT=600 FL=403 IP=210 FP=130 TP=0 TRAN CA=217 IS=1 FS=1 IT:330 FT=225 TT=3780 FL=260 IP=130 FP=40 TP=0 TRAN CA=218 IS=1 FS=1 IT=225 FT=100 TT=4500 FL=6700 IP=115 FP=115 TP=0 TRAN CA=219 IS=1 FS=1 IT=100 FT=100 TT=0 FL=226 IP=40 FP=1578 TP=0 TRAN CA=220 IS=1 FS=1 IT=70 FT=225 TT=60 FL=6700 IP=40 FP=40 TP=0 TRAN CA=221 IS=1 FS=1 IT=225 FT=70 TT=60 FL=6700 IP=40 FP=40 TP=0 TRAN CA=2 22 *IS=1 FS=1 IT=526 FT=130 TT=0 FL=389 IP=1050 FP=1050 TP=0 TRAN CA=223 IS=1 FS=1 IT=130 FT=526 TT=0 FL=389 IP=1050 FP=1050 TP=0 TRAN CA=224 IS=1 FS=1 IT=526 FT=375 TT=600 FL=458 IP=1050 FP=240 TP=0 TRAN CA=225 IS=1 FS=1 IT=375 FT=100 TT=9900 FL=334 IP=240 FP=40 TP=0 PAIR CA=201 CO=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 I File No.: V {-16Q-307 Page A49 of A51 Revision: 0 F0306-01 RO
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| | |
| V* StructuralIntegrityAssociates, Inc.
| |
| I I
| |
| 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 EX=8.5 *Tavg=545.5 EX=8.5 *Tavg=534.0 EX=8.5 *Tavg=534.0 I
| |
| PAIR CA=207 CO=10.4 DI=0.161 EX=8.5 *Tavg=534.0 PAIR PAIR PAIR CA=208 CO=I0.3 DI=O'.161 CA=209 CO=10.3 DI=0.161 CA=210 CO=9.9 DI=0.156 EX=8.5 *Tavg=521.0 EX=8.5 *Tavg=521.0 EX=8.5 *Tavg=413.0 I
| |
| PAIR CA=211 CO=9.8 DI=0.155 EX=8.5 *Tavg=400.0 PAIR PAIR PAIR CA=212 CO=9.8 CA=213 CO=9.9 CA=214 CO=10.4 DI=0.162 DI=0.155 DI=0.156 EX=8.5 *Tavg=400.0 EX=8.5 *Tavg=424.5 EX=8.5 *Tavg=537.5 I
| |
| PAIR CA=215 CO=10.0 DI=0.158 EX=8.5 *Tavg=462.0 PAIR PAIR PAIR CA=216 CO=9.5 CA=217 CO=9.2 CA=218 CO=8.7 DI=0.152 DI=0.149 EXý8.5 *Tavg=352.5 EX=8.5 *Tavg=277.5 DI=0.143. EX=8.5 *Tavg=162.5 I
| |
| PAIR CA=219 CO=8.3 DI=0.140 EX=8.5 *Tavg=100.0 PAIR PAIR
| |
| *PAIR CA=220 CO=8.6 CA=221 CO=8.6 CA=222 CO=9.4 DI=0.142 DI=0.142 DI=0.151 EX=8.5 *Tavg=147.5 EX=8.5 *Tavg=147.5 EX=8.5 *Tavg=328.0 I
| |
| PAIR CA=223 CO=9.4 DI=0.151 EX=8.5 *Tavg=328.0 PAIR PAIR CA=224 CO=10.0 DI=0.157 CA=225 CO=9.0 DI=0.147 EX=8.5 *Tavg=450.5 EX=8.5 *Tavg=237.5 I Re*9B.inp
| |
| * ------------------------------
| |
| *BEGIN REGION 9B TRANSIENT CARDS & GEOMETRY FOR RHR RETURN FROM VALVE NODE 660 TO PENET. NODE I
| |
| 675
| |
| -------------------------------
| |
| OPER CA=1 TE=100. PR=1100 I
| |
| OPER CA=2 TE=100 PR=50 OPER OPER OPER CA=3 CA=4 CA=5 TE=150 TE=150 TE=150 PR=1035 PR=1035 PR=1035 I
| |
| OPER CA=6 TE=150 PR=1035 OPER OPER OPER CA=7 CA=8 CA=9 TE=150 TE=150 TE=150 PR=1035 PR=1035 PR=1035 I
| |
| OPER CA=10 TE=150 PR=1160 OPER OPER OPER CA=11 CA=12 CA=13 TE=150 TE=150 TE=150 PR=1160 PR=700 PR=1035 I
| |
| OPER CA=14 TE=150 PR=1035 OPER OPER OPER CA=15 CA=1 6 CA=17 TE=150 TE=150 TE=150 PR=195 PR=115 PR=25 I
| |
| OPER CA=18 TE=100 PR=100 OPER OPER OPER CA=19 CA=20 CA=21 TE=100 TE=225 TE=70 PR=1563 PR=25 PR=25 I
| |
| OPER CA=22 TE=150 PR=1035 OPER OPER OPER CA=2 3 CA=2 4 CA=25 TE=150 TE=150 TE=150 PR=1035 PR=225 PR=25 I
| |
| TRAN CA=201 IS=1 FS=1 IT=70 FT=100 TT=1800 FL=204 IP=15 FP=1115 TP=0 TRAN CA=202 IS=1 FS=1 TRAN CA=203 IS=1 FS=1 TRAN CA=204 IT=100 FT=100 TT=1800 FL=204 IT=100 FT=150 TT=16164 FL=247 I P=1115 FP=65 IP=65 TP=0 FP=1050 TP=0 I TRAN CA=205 File No.: VY-16Q-307 Page A50 of A5 Revision: 0 F0306-O1R 0 I
| |
| | |
| V Structural Integrity Associates, Inc.
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| I TRAN CA=206 TRAN CA=207 TRAN CA=208 TRAN CA=209 TRAN CA=210 TRAN CA=211 TRAN CA=212 IS=1 FS=1 IT=150 FT=150 FL=429 IP=1175 FP=715 TP=0 TRAN CA=213 TRAN CA=214 TRAN CA=215 TRAN CA=216 IS=l FS=1 IT1=50 FT=150 TT=600 FL=403 IP=210 FP=130 TP=0 TRAN CA=217 TRAN CA=218 IS=l FS=1 IT=225 FT=100 q FL=6700 IP=115 FP=115 TP=0 TRAN CA=219 IS=1 FS=1 IT=100 FT1=00 FL=247 .IP=40 FP=157.8 TP=0 TRAN CA=220 IS=I FS=I IT=70 FT=225 FL=6700 IP=40 FP=40 TP=0 TRAN CA=221 IS=I FS=1 IT=150 FT=70 FL=6700 IP=40 FP=40 TP=0 TRAN CA=222 TRAN CA=223 TRAN CA=224 IS=I FS=1 IT=150 FT=150 FL=458 IP=1040 FP=240 TP=0 TRAN CA=225 IS=1 FS=1 IT=150 FT=150 FL=334 IP=240 FP=40 TP=0 PAIR CA=201 CO=27..6 DI=0. 521 EX=6. 4 *Tavg=85. 0 PAIR CA=202 CO=27.. 6 DI=0. 512 EX=6. 4 *Tavg=100.0 PAIR CA=203 CO=27.6 DI=0 .506 EX=6. 4 *Tavg=125.0
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| * PAIR CA=204 CO=27. 6 DI=0. 49 ) EX=6.4 *Tavg=150.0
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| * PAIR CA=205 CO=27. 6 DI=0.49_) EX=6.4 *Tavg=l50.0
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| *PAIR CA=206 CO=27. 6 DI=O. 49cS ) EX=6.4 *Tavg=150.0
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| * PAIR
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| * CA=207 CO=27. 6 DI=0.499) EX=6.4 *Tavg=l50.0
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| **PAIR CA=208 CO=27. 6 DI=0.49S EX=6. 4 *Tavg=150.0
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| *PAIR CA=209 CO=27. 6 DI=0.499 EX=6. 4 *Tavg=150.0
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| * PAIR
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| * CA=210 CO=27.6 DI=0.4 9S EX=6. 4 *Tavg=l50.0
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| *PAIR CA=211 CO=27 .6 DI=0.49S EX=6. 4 *Tavg=150.0 PAIR CA=212 CO=27.6 DI=0. 49S EX=6. 4 *Tavg=150.0
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| * PAIR CA=2113 CO=27 .6 DI=0. 499 EX=6. 4 *Tavg=150.0
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| *PAIR CA=214 CO=27 .6 DI=0.49S1 EX=6. 4 *Tavg=150.0
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| *PAIR CA=215 CO=27 .6 DI=0.. 49S1 EX=6. 4 *Tavg=150.0 PAIR CA=216 CO=27 .6 DI=0.499 1 EX=6.4 *Tavgl150.0
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| * PAIR CA=217 CO=27 .6 DI=0. 499 1 EX=6.4 *Tavg=150.0 PAIR CA=218 CO=27.6 DI=0.496 EX=6.4 *Tavg=162.5 PAIR CA=219 CO=27.6 DI=0.512 EX=b. 4 *Tavg=100.0 PAIR CA=220 CO=27 .6 DI=0. 500 EX=6. 4 *Tavg=147.5 PAIR CA=221 CO=27. 6 DI=0.509 EX=6. 4 *Tavg=110.0
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| *PAIR CA=222 CO=27. 6 DI=0.499 EX=6.4 *Tavg=150.0
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| *PAIR CA=223 CO=27.6 DI=0.499 EX=6.4 *Tavg=150.0 PAIR CA=224 CO=27.6 DI=0.499 EX=6.4 *Tavg=l50.0 PAIR CA=225 CO=27.6 DI=0.499 EX=.6. 4 *Tavg=150.0 File No.: VY-16Q-307 Page A51 of A51 Revision: 0 F0306-01 RO
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| APPENDIX B PIPESTRESS Output Output File Description Recirc 15.prf Fatigue results for reduced cycle count RHR 15.prf Fatigue results for full 60 year cycle count File No.: VY-16Q-30.7 Page B I of B5 Revision: 0 F0306-O1 RO
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| l" StructuralIntegrity Associates, Inc.
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| 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
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| ++ DST/PIPESTRESS ++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER . 3 CODE SECTION III CLASS I ASME-1998 RVP 2007/07/26 08:42:12 [42 Vermont Yankee Recirculation Fatigue Analysis FATIGUE ANALYSIS AT POINT. 600, WELDING TEE 600 TO 602 DELTA Ti IN DEGREES F INDIVIDUAL STRESS RANGE CHECK STRESSES IN PSI LOAD SET PAIR SALT OCCURENCES - -- NUMBER SETS NO. CYCLES USAGE REMARKS I J EQN. 14 NI NJ USED ELIMINATED TO FAILURE FACTOR DYNAM.
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| 11 21 88675. 10 150 10 2801. 0.0036 0 140 14 21 84491. 150 140 140 21 3359. 0.0417 10 0 19 20 67184. 1 150 1 19 8221. 0.0001 0 149 14 27 65876. 10 5 5 27 8900. 0.0006 5 0 45 10 20 62914. 5 149 5 10 10868. 0.0005 0 144 14 20 55493. 5 144 5 14 20012. 0.0002 0 139 9 20 54186. 35 13.9 35 9 22574. 0.0016 0 104
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| : 5. 20 53739. 290 104 104 20 23541. 0.0044 186 0 2 3 46216. 60 150 60 2 50502. 0.0012 0 90 1 26 46169. 60 5 5 26 50782. 0.0001 55 0 45 3 17 42799. 90 150 90 3 76939. 0.0012 0 60
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| : 6. 17 42219. 10 60 10 6 82911. 0.0001 0 50 150 5 18 42196. 186 150 18 83156. 0.0018 36 0 13 17 42131. 5 50 5 13 83864. 0.0001 0 45 8 17 41392. 35 45 35 8 92408. 0.0004 0 10 File No.: VY-16Q-307 Revision: 0
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| StructuralIntegrityAssociates, inc. I 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
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| ++ DST/PIPESTRESS ++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 3 CODE SECTION III CLASS 1 ASME-1998 RVP 2007/07/26 08:42:12 [421 Vermont Yankee Recirculation Fatigue Analysis FATIGUE ANALYSIS AT POINT 600, WELDING TEE 600 TO 602 DELTA TI IN DEGREES F1 INDIVIDUAL STRESS RANGE CHECK STRESSES IN PSI I LOAD SET PAIR r T SALT EQN. 14 NT OCCURENCES ------ ------
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| N.T NUMBER USED SETS ELIMINATED DYNAN.
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| NO. CYCLES TO FAILURE USAGE FACTOR REMARKS I
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| 7 1
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| 17 15 41326.
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| 38663.
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| 10 0
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| 55 0
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| 10 150 95 0
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| 10 55 7,17 1
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| 93222.
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| 133841.
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| 0.0001 0.0004 I 4 16 35177. 290 150 150 16 227086. 0.0007 140 0 4 is 34727. 140 95 95 15 246096. 0.0004 45 0 4 12 25167. 45 10 10 12 1449206. 0.0000 0
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| 35 26 27 23758. 45 45 45 ,27 26 1748766. 0.0000 DYN. RANGE OF EVENT NO.
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| 0 0 5 2773. 35 36 35 4 >100000000000. 0.0000 0 1 TOTAL USAGE FACTOR 0.0590 Notes a:
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| f:
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| j:
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| Fails Weld ISI Rupture Location I
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| IstructuralIntegrityAssociates, Inc.
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| RHR 15.prf D S T COMPUTER SERVICES S.A. F-4.2 PAGE NO. 401S
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| ++ DST/PIPESTRESS ++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 3 CODE SECTION III CLASS 1 ASME-1998 RVP 2007/07/26 08:44:06 [4-Vermont Yankee Recirculation Fatigue Analysis FATIGUE ANALYSIS AT POINT 641, SR ELBOW 640 TO 641 DELTA TI IN DEGREES F INDIVIDUAL STRESS RANGE CHECK STRESSES IN PSI LOAD SET PAIR SALT OCCURENCES ------ NUMBER SETS NO. CYCLES USAGE REMARKS I J EQN. 14 NI NJ USED ELIMINATED TO FAILURE FACTOR DYNAM, 10 20 100252. 300 10 10 1788. 0.0056 10 0 290 11 21 68706. 20 300 20 11 7511. .0.0027 0 280 12 20 64893. 20 290 20 9456., 0.0021 0 270 20 21 39947. 270 280 270 20 112120. 0.0024 0 10 3 21 35368. 300 10 10 21 219528. 0.0000 290 0 3 17 20439. 290 3 3190872. 0.0000 300 290 0 10 13 17 19221. 10 10 10 13,17 4148766. 0.0000 0 0 14 18 14925. 300 300 300 14,18 > 100000000000. 0.0000 0 0 15 19 14877. 300 1 1 19 100000000000. 0.0000 299 0 1 15 14434. 120 299 120 1 > 100000000000. 0.0000 0 *179 6 15 12896. 20 179 20 6 100000000000. 0.0000 0 159 9 15 12506. 70 159 70 9 > 100000000000. 0.0000 0 89 4 15 11542. 579 89 89 15 > 100000000000. 0.0000 490 0 7 27 10017. 20 5 5 27 > 100000000000. 0.0000 15 0 45 4 16 9993. 490 300 300 16 > 100000000000. 0.0000 190 0 File No.: VY-16Q-307 Revision: 0
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| StructuralIntegrityAssociates, Inc.
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| 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
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| ++ DST/PIPESTRESS ++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun
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| -. - . . . . .
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| - - - -. - -.-.
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| .- . -. .
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| -. - -.- -.- -.-. . -. . -. -.- -.- -.-. . .
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| -. .
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| -. -. - -. - -. - -. -.. -. . -.- -.- -. - -.- . .-. .-.
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| CALCULATION NUMBER 3 CODE SECTION III CLASS 1 ASME-1998 RVP 2007/07/26 08:44:06 [41 Vermont Yankee Recirculation Fatigue Analysis FATIGUE ANALYSIS AT POINT 641, SR ELBOW 640 TO 641 INDIVIDUAL STRESS RANGE CHECK DELTA T1 IN DEGREES STRESSES IN PSI I
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| LOAD SET PAIR I
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| 2 J
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| 7 SALT EQN.14 9353.
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| NI 120 OCCURENCES ------
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| NJ 15 NUMBER USED 15 7 SETS ELIMINATED DYNAM.
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| NO. CYCLES TO FAILURE
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| >100000000000.
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| USAGE FACTOR 0.0000 REMARKS I
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| 105 0 2
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| 5 26 5 9353.
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| 8235.
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| 105
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| .474 469 0
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| 579 474 0
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| 5 45 105 5 26 2 >100000000000.
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| >100000000000.
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| 0.0000 0.0000 I
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| I 26 27 2019. 45 45 45 ,27 26 >100000000000. 0.0000 DYN. RANGE OF EVENT NO.
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| 0 0 4 5 1570. 190 469 190 4 >100000000000. 0.0000 0 279 5 8 1512. 279 70 70 8 >100000000000. 0.0000 209 0 TOTAL USAGE FACTOR = 0.0128 I
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| Motes a: Fails f:
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| Weld ISI Rupture Location I
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| U File No.: VY-16Q-307 Revision: 0 I
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| I StructuralIntegrityAssociates, Inc. File No.: VY-16Q-308 "I. NEC-JH_ 11 CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME:
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| Environmental Fatigue Analysis of VYNPS CONTRACT NO.:
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| 10150394 CLIENT: PLANT:
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| Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE:
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| Core Spray Nozzle Finite Element Model Project Manager Preparer(s) &
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| Document Affected. Revision Description Approval Checker(s)
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| 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
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| I V StructuralIntegrityAssociates, Inc.
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| I Table of Contents I
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| 1.0 OBJECTIVE ................................................................................................................................... 3
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| .2.0 GEOM ETRY / M ATERIAL PROPERTIES ............................................................................ 3 I 3.0 4.0 PROGRA M IN PUT......................................... I.............................................................................
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| REFEREN CES ............................................................................................................................
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| 4 5 I APPENDIX A VYCSNGEOM.INP .......................................... Al I
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| I List of Tables I Table 1: M aterial Properties @ 300'F () .................................................................................. .......6 I
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| I List of Figures I
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| Figure 1: AN SYS Finite Elem ent M odel .......................................................................................... 7 I
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| I File No.: VY-16Q-308 Page 2 of 7 I
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| Revision: 0 F0306-0 RO I
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| 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.
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| 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:
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| (pressure)x (radius) 2 x thickness The equation for the membrane hoop stress in a cylinder is:
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| I (pressure)x (radius) thickness I The factor of two was verified in Reference [I I] where actual stress results were compared to the results of this analytical form.
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| The 2-D axisymmetric FEM was constructed using the dimensions and information from References
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| [1 -8] based on ANSYS [9] finite element software. Figure 1 shows the resulting finite element model.
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| The materials of the various components of the model are listed below:
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| :I
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| * Safe End - SB 166 [1] (72Ni-I5Cr-8Fe, N06600) 80 x 100 Conc. Reduction- SA312 TP304 [7] (18Cr-8Ni)
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| Nozzle Forging - SA508 Class I1[1] (3/4 Ni-l/2Mo-l/3 Cr-V)
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| * Vessel - SA533 Grade B [7] (Mn-1/2Mo-1/2Ni)
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| Cladding - SA240 TP 304 [7] (18Cr-8Ni)
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| 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.
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| File No.: VY-16Q-308 Page 3 of 7 Revision: 0 F0306-OIRO
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| StructuralIntegrityAssociates, Inc.
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| I I
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| 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 I applied to the FEM model for Green's Function development.
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| I 3.0 PROGRAM INPUT The input file, VY CSNGEOM.inp (included in Appendix A), creates the finite element model for I
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| the core spray nozzle.
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| ==4.0 REFERENCES==
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| : 1. Reactor 8 In. Dia. Nozzles Mk. N5A & B, 5920-00624 Rev. 8, SI File No. VY-16Q-207.
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| : 2. Core Spray Nozzle Weld Overlay Profile N5A & N5B, 5920-068i3, Sh. 1 of 2 Rev. 0, SI File No. VY-16Q-206.
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| : 3. N5A/B Thermal.Sleeve Details, 5920-00898, Rev 1, SI File No. VY-16Q-206.
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| : 4. Special Safe End Forging for Nozzles N2A/B & N5A/B, 5920-00655, Rev. 6, SI File No. VY-16Q-206.
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| : 5. Special Forgings for Nozzles N5A & N5B, 5920-00069, Rev 1, SI File No. VY-16Q-206.
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| : 6. Core Spray Nozzle Weld Overlay Profile N5A & N5B, 5920-06813, Sh. 2 of 2 Rev. 0, SI File No. VY-16Q-204.
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| : 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.
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| : 8. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition, 2000 Addenda.
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| : 9. ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004.
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| : 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.
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| : 11. SI Calculation No. VY-16Q-309, Revision 0, "Core Spray Nozzle Green's Functions".
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| File No.: VY-16Q-308 Page 5 of.7 Revision: 0 F0306-OIRO
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| StructuralIntegrity Associates, Inc. I I
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| Table 1: Material Properties @ 300'F ()
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| I Notes:
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| : 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].
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| : 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
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| : 3. Calculated as [k/(pd)]/12 3 .
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| !
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| AN0.
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| APIR 11ý 21007 i ,UM I- II: 12 :.16 L] ..........................
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| ELEMENPI3, APR; 11 2007 M4AT. -NUM 10:2 f 12:6 Core. 'Siray Nozzle Firnite Elem~ent Model Figure 1: ANSYS Finite Element Model File No.: VY-16Q-308 Page 7 of 7 Revision: 0 F0306-01 RO
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| APPENDIX A VYCSNGEOM.INP File No.: VY-16Q-308 Page Al of A17 Revision: 0 F0306-01 RO
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| I
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| !finish
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| /clear,start I/prep7 I et,I,PLANE182,,, 1 !Axisymmetric
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| /com, **************************
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| /com, Material Properties @T=300F
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| /com, ****************************
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| /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
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| /COM, Material #3 (Vessel: SA-533 Grade B, Mn-1/2Mo-1/2Ni)
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| 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
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| /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
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| * /com, *
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| /com, Geometric Parameters
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| /com, ****
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| *AFUJN,deg File No.: VY-16Q-308 Page A2 of A17 Revision: 0 F0306-0 I RO
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| I I
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| /com, pipe parameters
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| *set, pID, 9.834
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| *set, pOD, 10.815 I
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| *set, pL, 8 k, 1, pID/2, 0 I
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| k, 2, POD/2, 0 k, 3, POD/2, pL k, 4, PID/2, pL I
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| 1, 1, 2 1,2, 3 I
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| 1, 3, 4 1,4, 1 I
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| */com,**********
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| /com, Safe End Parameters I
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| /oom,**********
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| *set, seBX, pL
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| *set, selDOl, 9.834 I
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| .*set, seID02, 9
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| .*set, selD03, 9 + 31/32
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| *set, seID04, 11+ 3/4 I
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| *set,
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| *set, seOD01, seOD02, 10.815 11 + 1/6 I
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| *set, seOD03, 13 + 27/64
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| *set, seOD04, 10 + 11/16 I
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| *set, seLO1,
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| *set, seL02,
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| *set, seL03, 3 + 1/32 7/8 1+11/16 I
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| *set, seL04, 13/32
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| *set, seL05,
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| *set, seL06, 4
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| 3+1/2 I
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| *set, seLO7,
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| *set, seL08,
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| *set, seRO1, 12+4+/-1/16 seL07-(seLO 1+seL02+seLO3+seLO4+seLO5+seLO6) 3 I
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| *set, seR02,
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| *set, seR03,
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| *set, seR04, 3/4 1/4 1/8 I
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| .I k, 5, seOD01/2, seBX+seLO0 k, 6, seOD02/2, seBX+seLO 1+seL02 File No.: VY-16Q-308 Page A3 of A17 I
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| Revision: 0 F0306-0I RO I
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| 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
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| .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,,,
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| 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
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| /com, weld 1/8 gap
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| *set, wgap, 1/8 File No.: VY-16Q-308 Page A4 of A17 Revision: 0 F0306-OIRO
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| StructuralIntegrityAssociates, 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
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| /com, ***********
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| /com; Nozzle
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| /com, ***********
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| *set, nlDO1, seODO1
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| *set, nOD01, seOD03
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| *set, nOD02, 24+1/4
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| *set, nOD03, 2* 12+7.25
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| *set, nOD04, 2* 12+7.25-1-1/8
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| *set, nLOl, 4+5/16
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| **set, nL02, 5+3/8 I
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| *set, nL03, 5+1/8+5+5/8
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| *set, nWO1, 1/16 n
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| .*set, wClad, 3/16
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| *Set, wReactor, 5+5/8-wClad
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| *set, nL04, 7/16
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| *set, nR01, 1/4
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| *set, nR02, 3/16
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| * set, nR03, (8*12+7)*2
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| *set, nR04, 2.5
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| *set, nR05, nR04-wClad
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| *set, nR06, 3.5
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| *set, nR07, 3 +7/8
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| .*set, nR08, 0.5 u
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| K, 42, KX(11) + nWO1, KY(11)
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| K, 43, KX(41) + wClad, KY(41)+nLO4+nRO I K, 44, KX(43) + nROI, KY(43)
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| K, 46, KX(44) + nR01 *sin(15), KY(44)-nR01 *cos(15)
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| K, 47, KX(46) + 10*nR01 *cos(15), KY(46)+10*nRO I*sin(15)
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| 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)
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| K, 52, KX(51)+ 10*nROl*cos(15), KY(51)+10*nRO0*sin(15)
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| K, 53, KX(51) - 10*nRO0*cos(15), KY(51)-10*nR01*sin(15)
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| K, 54, KX(42), KY(42)+wClad*2 larc, 43, 46, 44, nR01 File No.: VY-16Q-308 Page A5 of A71 Revision: 0 F0306-01RO
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| StructuralIntegrityAssociates, Inc.
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| 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)
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| K, 65, 0, KY(63)-wClad K, 66, nR03+wClad, KY(62)
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| I .K, 67, 0, KY(65)-wReactor K, 68, nR03+wReactor, KY(62)
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| 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,,
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| LFILLT,33,47,nRO5,,
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| L, 50, 60 L, 60, 61
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| * LOVLAP, 40,46 File No.: VY-16Q-308 Page A6 of A17 Revision: 0 F0306-OIRO
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| V Structulral integrityAssociates, Inc.
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| LDELE, 50, 51 i LFILLT,49,52,nRO6 LFILLT,38,41,nR07 LFILLT,49,38,nRO8
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| /com, Nozzle and Vessel border K, 80, nODO3/2, KY(60)+/-2*nLO3 K, 81, nOD03/2, KY(60)
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| K, 82, nOD4/2, KY(60)+/-2*nLO3 K, 83, nOD04/2, KY(60)
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| 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,,
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| KL,34,0.5,,
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| KL,32,0.5,,
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| LSTR, 78, 79 LSTR, 79, 84 K, 90, KX(73)+wReactor*2*cos(160), KY(73)+wReactor*2*sin( 160)
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| 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)
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| 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
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| StructuralIntegrityAssociates, Inc.
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| I
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| /com, ***********
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| /com, Weld Overlay
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| /CON,************
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| I *set, woA, 3.100
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| *set, woB, 0.781
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| *.set, woC, 2.500 I *set, woD, 3.734
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| *set, woE, 3.480
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| *set, woF, 6.3 10 I *set, woG, 8.313
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| *set, woH, 0.535
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| *set, woR0l, 7/16 i K, 80, KX(40), KY(40)-wgap/2-woA K, 81, KX(80)+woH, KY(80)+woH U K, K,
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| 83, KX(40), KY(40)-wgap/2+woB/2+woC 82, KX(83)+woH, KY(83)-woH I L, 80, 81 L, 81, 82 I L, 82,83 LPTN, 74, 46 I LDELE, 79 LFILLT,78,76,woR0 1,,
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| LSTR, 94, 96
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| /com,
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| /com, Heat transfer coef. points S /tom, *************
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| * set, tsLO1, 2.25
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| *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
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| Structural Integrity Associates, Inc.
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| V 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)
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| 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)
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| K, 107, KX(38)+wReactor*cos(160), KY(38)+wReactor*sin(160)
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| L, 99, 106 I
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| 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 LCOMB,1 11,24,0 I
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| LDIV, 11,, ,3,0 K, 110, KX(22)+wReactor*cos(180), KY(22)+wReactor*sin(180)
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| L, 110, 22 1 LPTN, 15, 89 LDELE, 94 File No.: VY-16Q-308 Page A9 ofA17 i Revision: 0 F0306-01 RO I
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| C StructuralIntegrity Associates, Inc.
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| LSTR, 28, 111 LSTR, 27, 22 LSTR, 17, 7 K, 112, KX(33)+wReactor, KY(33)
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| L, 33, 112 LPTN, 7, 95 LDELE, 99 K, 114, KX(25)+wReactor*cos(180), KY(25)+wReactor*sin(180)
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| L, 114,25 K, 115, KX(8)+wReactor*cos(180), KY(8)+wReactor*sin(180)
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| L, 115,8 LPTN, 95,17 LPTN, 7,101 LDELE, 102,103
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| /com,**************
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| /com, Creating Areas and Meshing
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| /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
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| Structural integrityAssociates, 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
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| StructuralintegrityAssociates, Inc.
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| 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)
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| 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.
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| LDELE, 9 LSTR, 42,. 11 LSTR, 42, 10 LESIZE, 8, ,,2 .....
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| 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
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| StructuralIntegrityAssociates, Inc.
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| 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
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| StructuralIntegrityAssociates, Inc.
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| 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
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| Structural Integrity Associates, Inc.
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| MAT,4 LESIZE, 33.,,2
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| ! Clad U 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 LESIZE, 57,,,2
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| ! Clad 3 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*
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| LESIZE, 42,,, 2 AL, 57, 56, 42, 55 AMESH, 30 I
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| 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
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| .Revision: 0 F0306-0 1RO I
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| VStructuralIntegrityAssociates, Inc.
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| 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
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| /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)
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| 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
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| ****,***********************
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| /COM, HTC point of Region 7 MAT,4 ! Clad ACLEAR, 18 ADELE, 18 K, 122, KX( 14)+wReactor, KY(14)
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| L, 14,122 LSBL, 84, 71 File No.: VY-16Q-308 Page A16 of A17 Revision: 0 F0306-01 RO
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| StructuralIntegrityAssociates, Inc. U LESIZE, 72,,,10 i LESIZE, 74,,, 10 AL, 66, 30,45,79,72,74 AMAP,18, 100, 10 1,99,109
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| /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
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| /*I
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| /COM, Define DOFconstraints on lines
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| *** ** *** ** **
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| DL,42, ,SYMM DL,44, ,SYMM FLST,4,9,1,ORDE,2 FITEM,4,1 FITEM,4,-9 I CP, 1,UY,P51X I
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| I I
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| I File No.: VY-16Q-308 Page A17 of Al7 Revision: 0 F0306-01 RO I
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| -StructuralIntegrity Associates, Inc. File No.: VY-16Q-309 NEC-JH_12 CALCULATION PACKAGE Project No.: VY-16 Q PROJECT NAME:
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| Environmental Fatigue Analysis of VYNPS CONTRACT NO.:
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| 10150394 CLIENT: PLANT:
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| En~terg~y Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE:
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| 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
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| Structural IntegrityAssociates, Inc.
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| Table of Contents 1.0 OBJECTIVE .................... ...................................................................... 4 2.0 CORE SPRAY NOZZLE MODEL DESCRIPTION................................................. 4 3
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| .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
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| | |
| ==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 -
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| 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 Revision: 0 Page 2of 32 3 F0306-OIRO
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| V StructuralIntegrityAssociates, Inc.
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| 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 Page 3of 32 Revision: 0 F0306-01 RO
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| I V StructuralIntegrityAssociates, Inc.
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| I 1.0 OBJECTIVE I 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 I Station Core Spray Nozzle.
| |
| I 2.0 CORE SPRAY NOZZLE MODEL DESCRIPTION An axisymmetric finite element model of the core spray nozzle was developed in Reference [1] using I
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| 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 5000 F to 100°F, which will be applied to the FE model for Green's Function U
| |
| development. Table 1 lists the material properties at.300°F. The meshed model is shown in Figure 1.
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| I I
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| I I
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| I I
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| I I
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| I I
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| File No.: VY-16Q-309 Page 4 of 32 I
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| Revision: 0 F0306-0 IRO I
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| V StructuralIntegrityAssociates, Inc.
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| Table 1: Material Properties @ 300°F ()
| |
| Coefficient Modulus of of Thermal Thermal 0 Part MaeilDiffusivity, Elasticity, e+6 Expansion, Conductivity, Thermal Btu/Ib-Heat, Specific F Ra Pois Description psi e-6, Btu/hr-ft-0 F ft2/hr 1C] (3) INU
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| [EXI in/in/IF [KXXI
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| [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.
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| Cr-V SA533 Mn-n0.13.
| |
| Vessel Gade 1/2Mo- 28.0 7.7 23.4 0.401 0.1193 0.
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| Grade B l/2Ni SA240 3/16 Clad TP304 80 x 100 SA312 Con.( 2 Reduction(2 TP304 P0 18Cr-8Ni 27.0 9.8 9.8 0.160 0.1252 0.
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| 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(
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| values [3].
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| : 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 .
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| Fie No.: VY-16Q-309 Revision. 0
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| V* StructuralIntegrityAssociates, Inc.
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| Core Spray Nozzle Finite Element Model Figure 1: ANSYS Finite Element Model File No.: VY-16Q-309 Page 6 of 32 Revision: 0 F0306-OI RO
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| I Structural IntegrityAssociates, Inc.
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| 3.0 APPLIED LOADS Both pressure and thermal loads were applied to the finite element model.
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| 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:
| |
| P-D 2 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.
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| File No.: VY-16Q-309 Page 7 of 32 Revision: 0 F0306-OI RO
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| StructuralIntegrityAssociates, Inc.
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| I I
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| I I
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| Core Spray Nozzle Finite Element Model I Figure 2: Core Spray Nozzle Internal Pressure Distribution I
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| I I
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| File No.: VY-16Q-309 Page 8 of 3K Revision: 0 F0306-01 RC
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| V StructuralIntegrity Associates, Inc.
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| Core Spray Nozzle Finite Element Model Figure 3: Core Spray Nozzle Pressure Cap Load File No.: VY-16Q-309 Page 9 of 32 Revision: 0 F0306-01 RO
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| StructuralIntegrity Associates, Inc.
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| Core Spray Nozzle Finite Element Model Figure 4: Core Spray Nozzle Vessel Wall Boundary Conditions File No.: VY-16Q-309 Page 10 of 32 Revision: 0 F0306-OIRO
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| I(
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| SStructuralIntegrityAssociates, Inc.
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| I
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| * 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°F to develop the stress response on the core spray nozzle in the stagnant Condition.
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| The 100% flow case simulates operational condition of the core spray nozzle (i.e., the entire core spray I nozzle experiences 100°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.
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| For both Green's Functions, a 500F - 100l F thermal shock was run to determine the stress response.
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| 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.
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| 1 3.2.1 Boundary Fluid Temperatures For the Green's Functions, a 500OF - 100°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).
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| 3 3.2.2 Heat Transfer Coefficients Figure 5 shows where the heat transfer coefficients were applied to the FEM for the 0% (steady-
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| * 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-fi2-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].
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| 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.
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| * File No.: VY-16Q-309 Page 11 of 32 Revision: 0 F0306-01 RO
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| C Structural integrityAssociates, Inc.
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| Region 10 Region 11 Region 7 Region 12 Region 6 Regi Region 4_
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| Region 1 Figure 5: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries (not to scale) I I
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| File No.: VY-16Q-309 Pa*ge 12 of 32 I Revision: 0 F0306 OIRO I
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| S Table 2: Heat Transfer Coefficients 0% Flow 100% Flow Regions Initial HTC Initial HTC Temperature °F Btu/hr-ftZoF Temperature IF Btu/hr-ft2_oFF 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°' 500 38 500 50 R7B '1 500 20 500 23 Kll 5O00 :-hte~r a~ ~ 55O1 hrpollatcd
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| __ R9 (_) 500 33 500 41 10________
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| ___\____ hiipolatd50 ___A_____
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| RIH 500 500 500 500 R12 120 0.20 . 120 0.2 (1) See Table 13 File No.: VY-16Q-309 Page 13 of 32 Revision: 0 F0306-O1 RO
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| I C StructuralIntegrityAssociates, Inc.
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| I Table 3: Heat Transfer Coefficients for Region 1 I
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| Pipe Inside Diameter, D 0 9.834 inches = 0.820 ft 100% rated flow= 3,200 gpm Flow, % of rated =
| |
| Fluid Velocity, V =
| |
| Characteristic Length, L = 0 =
| |
| 100%
| |
| 13.517 0.820 ft/sec ft=
| |
| 0.250 3,200.0 0.250 m
| |
| gpm 1.234236214
| |
| @T=
| |
| Density, p =
| |
| Mlb/hr 549 48.087
| |
| -F ibmift 3
| |
| iI TUd - T.ý-, AT = assumed to be 12% of fluid temperature = 8.40 12.00 24.00 36.00 48.00 60.00 72.00 -F I
| |
| NO.e:Th. abo.e -10rri- i. base -n e-"ei-n -1wfh °C 5 4.67 6.67 13.33 20.00 26.67 33.33 40.00 R'Vhest transteronsty*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-'C
| |
| ... T-.LC I
| |
| 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-°C
| |
| ....
| |
| ... .~ _
| |
| H~A . ~~~~~~~~~~~
| |
| ~ ......................... ............... .... .. 000 I........e* ._0...
| |
| 1.010 1.030 .....................
| |
| 1..0......... ............
| |
| .....................................-.......
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| ..........................................
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| 0.998 . 080..
| |
| 1.080 . .... ..............1.190 1... 1.510 I..............
| |
| . ...................... B
| |
| ........
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| Bl/bm' 3
| |
| p .16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3
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| ._(.Density) 62.3 62.1 60.1 57.3 53.6 49.0 42.4 Ibm/ft 3
| |
| I 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 1m3.C
| |
| .......
| |
| (V ~...
| |
| meri. Rate (Volumetric a *~ ... -! ........1-5_
| |
| _anE o! .....................................
| |
| of Expansion) 1.05E-04 .......... 1 1.80E-04 .R4..............
| |
| .3.70E-04 --............ .....
| |
| .2E ........
| |
| 5.60E-04 ................ E O.:_
| |
| 7.806-04 ..I..
| |
| .............. O.E.-.
| |
| 1.10E-03 ......... .........
| |
| . _...
| |
| 1.75E-03 3.......
| |
| ...... ...
| |
| ..... 3 !.
| |
| f /fe '
| |
| 3...
| |
| ? ...
| |
| 2 g 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 Mrs
| |
| .....Constant o~ a n ) .. ................. .......
| |
| Gfsv~ati ...... .... .. .......
| |
| 332.17 . .....................3.
| |
| .2=
| |
| .. 1...7..
| |
| .......- - ---. 2
| |
| .......32.17 ...... ..... ...... 3.2...
| |
| 32..17..................... ....... ... ... . 32.17 332.17 2?. .1............... ........
| |
| .... _. 1 .. .. ......
| |
| ffj .2 =...
| |
| ............. ....
| |
| ...... .......
| |
| nal.£
| |
| ....(G~ravit-ational 32.17 32.17 32.17 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 I
| |
| ....... .......... .......... .......- . .6. 9-0 4.8.0 04 1.0.0 93E0.950 5 7.00 0.859 -05 . 7605 1.070 Imf-s --.
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| Pr . 6.980 4.510 1.910 1.220 (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 --
| |
| 2 Grashof Number, Gr gPATL/(gJp) 1.3522E+08 7.0314E+08 1.3383E+10 6.9351E+10 2.2021E+11 5.7264E+11 1.1964E+12 --
| |
| From [4].
| |
| Rayleigh Number, Ra Inside Surface Forced Convection Heat Transfer Coefficient:
| |
| H._, = 0.023Re Pr°'k/D GrPr 55 9.4382E+08 7,765.07 3.1712E+09 9,25725 2.5562E+10 13,05072 8.4608E+10 15,291.12 2.0920E+11 16,581.64 4.9189E+11 16,999.27 1.2802E+12 16,154.74 W/m _°C 2
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| I 2
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| 1,367.53 1,M.33 2,298,41 r-V - ? ' .2,920.25 2 1.Z845,07 Btu/hr-ft -'F I
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| 2 3.1458-03 4.434E-03 5 I.15803 5.63E03 577SE-03 5.4882-03 Btulsec-in -- F Bt2.63803 From [41:
| |
| Inside Surface Natural Convection Heat Transfer Coefficient:
| |
| Case: Enclosed cylinder . C= -.0 n= (see *agt.256 o [4]
| |
| 2 Hýý= C(GrPr)'k/L 231.44 329 18 59732 811.84 984.52 1,11382 1,18770 W/m _oC 4
| |
| 7.863E-05 520
| |
| .1 .11S.04 .~2.029F-04 I73-39 2 758E-04 3.34SE-04 -<
| |
| 19616 3.784E 209.17
| |
| >.(4.035L,01~
| |
| Btu/ser-fin-'F Btu/sec-in 2
| |
| _,F I
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| File No.: VY-16Q-309 Revision: 0 Page 14 of 32 I
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| F0306-01 RO
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| VStructuralIntegrityAssociates, Inc.
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| I Table 4: First Partial Heat Transfer Coefficients for Region 3 Pipe Inside Diameter, D = 7."I. I inches 0665 ft 100% rated flow = 3,200 gpm
| |
| = 0.203 m @T= 549 -F Flow, % of rated - i00>* Density, p =' 48.087 Ibm/ft' Fluid Velocity, V = 20.522 ftlsec = 3,200.0 gpm = 1.234236214 Mlb/hr Characteristic Length, L = D = 0.665 ft = 0.203 m Týý -T*, AT = assumed to be 12% of fluid temperature = 8.40 12.00 24.00 36.00 48.00 60.00 72.00 -F
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| ,Vole:Thoaboe*se,,n o~d ope,,iense*lh = 4.67 6.67 13.33 20.00 26.67 33.33 40.00 °C
| |
| : p. SRPV hlea -*yrn-aly 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-°C n t 0.3465 0. 3640. 3920 0.3950 .3820 0.3490 0.2930 Btuthr-ft-°F C 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJikg-°C
| |
| (..i!9H 1M00 0.996 - 1.010 1.030 1.080 1.190 1.510 Btullbm-ýF p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/in 3
| |
| (.es .. .. 2............
| |
| : 62. 62 . 60.1 57.3 53.6 49.0 42.4 Ibm/ft 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 3 3 (Volumetric, Rate of Expansion) 1.05E-04 1.80E-04 3.70E-04 5.60E-04 7.80E-04 1.1OE-03 1.75E-03 ft ,f,-'F g 03048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 m/s2 2
| |
| (Gravitational 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
| |
| ....... ........................- 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 3 2 Grashof Number, Gr g)IATL /(plp) 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 ForcedConvection Heat TransferCoefficient:
| |
| 2 H.*a- 0.023ReoePr°41Dk 11,307.23 13,480 10 19,004.02 22,266+42 24,145.63 24,753.78 23,524.01 W/m -°C 94,14290 Btu/hr-ft.-°F 2
| |
| 3..841E-.03 4-580E-03 ,6.45GE.03 /~.564E-03 8.203E-03 .7 .409E-W~ 7,92E-03' 31u/sec-,n -F From [4]:
| |
| Inside Surface NaturalConvection Heat Transfer Coefficient:
| |
| Case: Enclosed cylinder C 0.5 n= p 2
| |
| Hse = C(GrPr)nlkL 243:85 346.81 629.32 85534 1,03727 1.173.50 1,251 33 W/m -°C
| |
| ~ ~ ~~~~
| |
| 12.94 M8 ~ ~610 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
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| 'Page 15 of 32 File No.: VY-16Q-309 Page 15 of 32 Revision: 0 F0306-O IRO
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| I StructuralIntegrity Associates, Inc.
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| I Table 5: Second Partial Heat Transfer Coefficients for Region 3 I Pipe Inside Diameter, 0 =
| |
| * Outer Pipe, Inside radius, r. =
| |
| ,
| |
| 4.917 inches inches 0.820 0.250 0.410 0.125 m
| |
| ft ft m
| |
| I Inner Pipe Outside Diameter, 0 = 2 inches = 0.719 ft Inner Pipe, Outside radius. r =
| |
| Fluid Velocity, V = 13.517 4.3125 inches =
| |
| ft/sec =
| |
| 0.219 0.359 0.110 m
| |
| ft m
| |
| gpm I
| |
| Characteristic Length, L = D = 0.820 ft = 0.250 m (Outside) T, - T,,~, AT = 840 12.00 24.00 36.00 48.00 60.00 . 72.00 'F Water Property Conversion Factor [4]
| |
| =
| |
| 70 21.11 4.67 100 37.78 6.67 200 93.33 13.33 148.89 20.00 Value at Fluid Temperature, T 7]
| |
| 300 400 204.44 26.67 500 260.00 33.33 600 315.56 40.00 'C Units
| |
| 'F
| |
| °C I
| |
| I k 1.7307 0.5997 0.6300 0.6784 0.6836 0.6611 0.6040 0.5071 W/m-'C
| |
| ...... . ml ............. ...... 0 0.3465 5. 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
| |
| . ..........
| |
| .. Heat)....9 . 0 .. . 00 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 3
| |
| I (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 3
| |
| (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 1ft -'F . .
| |
| .......
| |
| 2 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 I
| |
| 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... -04ý 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 --
| |
| I 3 2 Grashof Number, Gr gp3ATL/(p/p) 135217684.2 703144247.6 13383382850 69350803914 2.2021E+11 5.72636E+11 1.19642E+12 --
| |
| 3 3 Grashof Number, Grý g93AT(r,-rj) /(Pjp) 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 Gr5 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 NaturalConvection Heat Transfer Coefficient:
| |
| Case:
| |
| Hsee Enclosed cylinder C(GrsPr)nlk(r,-) 18278
| |
| ,".3219 C=
| |
| 24468 4309 0d 40000 70.45 n=
| |
| 512.07 "0
| |
| 593.51 104 53 -
| |
| ('sie .- Agc29 643.36 1t1330 o 15])
| |
| :11518 653 99 Wlm -oc Btu/hr-ft 2
| |
| 2
| |
| -'F I
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| I I
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| I I
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| I I
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| File No.: VY-16Q-309 Page 16 of 32 I
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| Revision: 0 F0306-01 RO I
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| | |
| 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 100% rated flow = 3;200 gpm 0.203 m @T= 549 -F 3
| |
| Flow, % of rated = 0 Density, p = 48.087 Ibm/ft Fluid Velocity, V = 20.522 fl/sec = 3,200.0 gpm 1.234236214 Mlblhr Characteristic Length, L== D 0.665 ft = 0.203 m Tý,w - T==am, AT = assumed to be 12% of fluid temperature = 8.40 12.00 24.00 36.00 48.00 60.00 72.00. -F
| |
| ,oe.. 7h., b-, . t, . ,, Weh = 4.67 6.67 13.33 20.00 26.67 33.33 40.00 °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-°C
| |
| .. Thermal Conductivity) 0.3465 0.3640 0.3920 0.3950 0.3820 0.3490 0.2930 Btu/hr-ft-°F Cv 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-°C
| |
| ~ ai 1.0. 0082.3~ 0 ~ 4 1.190, 151 Btu/Ibm-'F 3
| |
| 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 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 lm _-c 3
| |
| (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 /ft_-.F 2
| |
| g 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9806 mls (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 " -°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 -
| |
| 3 2 Grashof Number, Gr g1ATI- (pip) 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 ForcedConvection Heat Transfer Coefficient:
| |
| 8 2
| |
| = 0.023Re Pr°'k./D 11,307.23 13,48010 19,00402 22,266.42 24,14563 24,75378 23,52401 W/m -oC 2
| |
| 1,<991.36 2,737403 3468
| |
| .5E0 .ýL0 4,22.8
| |
| .0E0
| |
| , 4,359-48 49-3 4,142-90 792-3 Btu/hr-ft .-F
| |
| , Btu/sec-in 3.4E0 .8E0 2° From [4]:
| |
| Inside Surface Nlatural Convection Heat Transfer Coefficient:
| |
| ,Case: Enclosed cylinder 0= 055 n 0.25"of (see page
| |
| *41) 29 2
| |
| He C(GrPr)'kJL 24385 346 81 62932 85534 1,037.27 1,17350 1,251.33 Wlm1-C 2
| |
| 42.94 : 61.081 110,83 f 10O , 182.68. ,. 206,67 : <, 220.38 Btu/hr-f -"F 2
| |
| 8.284E- 1.17BE.04 2138E4 2.906E 0 1 -24E-04 19M-04 4.25iE-04 Btu/sec-in -°F File No.: VY-16Q-309 Page 17 of 32 Revision: 0 F0306-01 RO
| |
| | |
| StructuralIntegrity Associates, Inc.
| |
| I I
| |
| Table 7: Second Partial Heat Transfer Coefficients for Region 5 I Title i
| |
| N,= wP , ýI ý, nLi-ý ýýýý 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 Inner Pipe, Outside radius, ri Fluid Velocity, V =
| |
| 4.3125 inches 0.219 0.359 0.110 m
| |
| ft m
| |
| I 16.138 ftsec - I gpm Characteristic Length, L = D = 0.750 ft = 0.229 m (Outside) T,, - T,-, AT 8.40 12.00 24.00 36.00 48.00 60.00 72.00 Water Property Conversion Factor [4]
| |
| 70 21.11 4.67 100 37.78 6.67 200 93.33 13.33 Value at Fluid Temperature, T M7]
| |
| 300 148.89 20.00 400 204.44 26.67 500 260.00 33.33 600 315.56 40.00 Units
| |
| -F
| |
| °C I
| |
| h)e k -- 1.7307.................. .00.5997
| |
| * 5............. 0.6300 ........ 00.6784 ....................................
| |
| I
| |
| ............... ! . ... ... ... ......... 0.6836
| |
| =3 5O.. .... 0.6611 0.6040 0.5071 W/m-°C I(m 1-1n- 0.3_6 1Q0 :3 .. ..... .
| |
| .3 2 .. ............ = .4.9 o2 3
| |
| * r_ ° 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-°C
| |
| ..................
| |
| ..........
| |
| (Sp..2ý ,ic.Heaýt9................
| |
| .... ........... ...............................
| |
| ..... ...............1 999.0.0
| |
| .........................
| |
| 0.9 .......... 1 0. q.1. ................. 1..0._, .....
| |
| . . .... 1: . ...... ...... :1 0 . ............. 1 .= ............ .tufm .ý-*.
| |
| 3 p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3
| |
| I (Density) 62.3 62.1 60.1 57.3 53.6 49.0 42.4 Ibm/ft
| |
| .1.8 1,89E-04 3 3 3.24E-04 6.66E-04 1.01E-03 1.40E-03 1.98E-03' 3.15E-03 m lm -°C
| |
| .. .........
| |
| !(Volumetric o....
| |
| _ .e !.... -Rate
| |
| ............ . n*o .}...........
| |
| of Expansion) ..............
| |
| ..................
| |
| .......
| |
| .... ..... .......
| |
| ... O. E. ..................
| |
| ...........
| |
| 1.056-04 L1.80E-04 80.-.. ...........................
| |
| *3.70E-04
| |
| .0_............... *5.60E-04
| |
| -...
| |
| .* .......................
| |
| ._9 *.....
| |
| 7.80E-04 .....
| |
| .....
| |
| -:.0_.. ..................
| |
| 1.10E-03 . .E. l.
| |
| . .......
| |
| 1.75E-03 .... . ** ft /tt *2-F.........
| |
| 3 3 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
| |
| .. .(y
| |
| ..........-
| |
| 1 R..........
| |
| iVs Pr (Prandtl Number)
| |
| Calculated Parameter 4ýninc.V
| |
| . y.co
| |
| ) .. . ............
| |
| ...............
| |
| 1.4881
| |
| .. .....................
| |
| Formula 9.96E-04
| |
| . .......... 9.:-........
| |
| 6.696-04 6.980 70 6.82E-04
| |
| ' ... .............
| |
| :.5.............
| |
| 4.586-04.2.006E-04 4.510 100 3.07E-04 I...........
| |
| ..2... 0.....
| |
| 1.910 200
| |
| -0..
| |
| 1.93E-04
| |
| ...................
| |
| ..11.306-04
| |
| .E............
| |
| 1.220 300 1.38E-04
| |
| ..........
| |
| 99.30E-05 0.950 400 1.04E-04
| |
| =-5-9 .....................
| |
| 7.006-05 0.859 500
| |
| *.=g
| |
| ........
| |
| ..........
| |
| 8.62E-05
| |
| .....
| |
| . 0=
| |
| 5.79E-05 1.070 600 kg/i-s
| |
| .......... . .!Ib/ts
| |
| ** .....
| |
| --
| |
| -F I
| |
| Reynold's Number, Re pVD/p 1126238 1641130 3531215 5334924 6975877 8472567 8863480 --
| |
| Grashof Number, Gr Grashof Number, Gri Rayleigh Number,.Ra Rayleigh Number, Ra goATL /(Ipp) g0AT(r _r) /(p!p)
| |
| GrPr 3
| |
| Gr ý Pr 3
| |
| 2 3
| |
| 103650263.4 538990790.5 10258947757 53160421562 1.68801E+11 9.37E+02 723478838.9 6.54E+03 4.87E+03 9.28E+04 2430848465 19594590215 64855714305 1.60361E+11 2.20E+04 1.77E+05 4.81E+05 5.86E+05 1.53E+06 1.45E+06 4.3895E-11 3.97E+06 3.77058E+11 3.41E+06 9.17108E+11 8.29E+06 9.81306E+11 8.87E+06
| |
| --
| |
| --
| |
| --
| |
| I I
| |
| From [4]:
| |
| Annulus NaturalConvection Heat Transfer Coefficient:
| |
| Case: Enclosed cylinder 2 C n1 238.7of [5p 2
| |
| titeC(GrsPr)kl(r 0 ri) 291.94 390.80 638 87 817.88 94795 1,027 56, 1,044 55 W/im -tc
| |
| . 5 5411,. . 68.83 112.51 1,G.16950 , 180.97 - 18396 Utu/hir-fe,- F.
| |
| I I
| |
| I I
| |
| I I
| |
| File No.: VY-16Q-309 Page 18 of 32 Revision: 0 F0306-O1RO I
| |
| | |
| V Structural Integrity Associates; Inc.
| |
| Table 8: First Partial Heat Transfer Coefficients for Region 7 Pipe inside Diameter, D = i7j I inches = 0.665 ft 100% rated flow = 3,200 gpm
| |
| = 0.203 m @T 549 °F 3 Flow, % of rated= "100%, Density, p = 48.087 Ibm/ft Fluid Velocity, V = 20.522 ftlsec 3,200.0 gpm 1.234236214 Mlbthr Characteristic Length, L = D = 0.665 6f= 0.203 m TO, - T,,.,um, AT = assumed to be 12% of fluid temperature 8.40 12.00 24.00 36.00 48.00 60.00 72.00 °F Woe Theaboe r I bed on exeriee h 467 6.67 13.33 20.00 2667 33.33 4000 rC p*aPVvt.tI*,snter ana~y... . 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 0.6784 0.6836 0.6611 0.6040 0.5071 W/m-°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-°C
| |
| ....... e p~ i.8(L 1.00. 0..998 010 1.00 1N..080 .190 .. 1._t* m-'F.*
| |
| 3 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 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 /m -°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 2
| |
| 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 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 °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 3 2 Grashof Number, Gr goATL /(igp) 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 TransferCoefficient: 2 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 .°C 2
| |
| 371403 . 3 T4 3 <8174,242,8 -, ?,q435:8 1" Btulhr-ft 2
| |
| 3.lE1E03 >4580E-.03> 6,1566I03.Y 7.4E203. 8, 2603E'13. F,, -0 7.92ET-43~ 3 tu/sec-in -- F From [4]:
| |
| Inside Surface NaturalConvection Heat TransferCoefficient.
| |
| Case: Enclosed cylinder n -f 0 2 [4])
| |
| 2 Hfte, C(GrPr)nk/L 243.85 346.81 62932 85534 1,03727 1.173.0 1,251.33 W/m -°C 4 7ý. i6 1'08' ' 11083, e'<8:8- ""; 206.,7 2-1 ' ý' 2'
| |
| ~2844t 2 05' >~1 78E-0 2 1386-4 '"1 2 A1 -1.2E0 '0 3 9,-7E -04~i _________i'-*
| |
| File No.: VY-16Q-309 Page 19 of 32 Revision: 0 F0306-0I RO
| |
| | |
| StructuralIntegrity Associates, Inc. I I
| |
| Table 9: Second Partial Heat Transfer Coefficients for Region 7 Pipe Inside Diameter, D = 1 o*~ inches= 0.835
| |
| * ft U
| |
| 0.255 m Outer Pipe, Inside radius, r. =
| |
| Inner Pipe Outside Diameter, D =
| |
| 5.01 inches =
| |
| inches 0.418 0.127 0.719 0.219
| |
| .m ft ft m
| |
| I Inner Pipe, Outside radius, r = 4.3125 inches = 0.359 ft I
| |
| 0.110 m Fluid Velocity. V = 13.020 ft/sec = '20ý gpm Characteristic Length, L = 0 = 0.835 ft = 0.255 m (Outside) TT - T, AT
| |
| = 8.40 12.00 24.00 36.00 48.00 60.00 72.00 °F
| |
| - 4.67 6.67 13.33 20.00 26.67 33.33 40.00 C WaterProperty k
| |
| Conversion Factor [4]
| |
| 1.7307 70.
| |
| 21.11 0.5997 100 37.78 0.6300 200 93.33 0.6784 Value at Fluid Temperature, T [
| |
| 300 148.89 0.6836 400 204,44 0.6611 500 260.00 0.6040 600 315.56 0.5071 Units W/m-°C
| |
| °F C
| |
| I I
| |
| Thermal Conductiv)----------------03465 0.3640 0.39 0.3950 0820. 03490 . 0 -2930 tu/hr-ft-°F c 4.1869 4.185 . 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-°C
| |
| ........~e c~c . ._Sp
| |
| !_ .. ........ .... ... ........-. 1-1.:000
| |
| ..... 099.9 9 8 .1..00..........1...030. ........ 01 8 0.0,_119..
| |
| ..... .. 1.519_0.......
| |
| . ..... tut151 -m 3
| |
| ° 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m p
| |
| 3 (Density) 62.3 62.1 60.1 57.3 53.6 .. 490 42.4 . bm/ft 3 3 I
| |
| S1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 140E-03 1.98E-03, 3.15E-03 m 3/m3 -C (Volumetric Rate of Expansion) 1.05E-04 1.80E-04 .. 70E-04 ...... 60-04 7.80E-4 .. .1E03 . .75E-03 ft /t -oF 2 9 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 mrs (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 (Prandtl Number)
| |
| Calculated Parameter Reynolds Number, Re Formula pVD/p 3 2 6.980 70 1011591 4.510 100 1474069 1.910 200 3171750 1.220 300 4791848 0.950 400 6265758 0.859 500 7610090 1.070 600 7961209
| |
| 'F
| |
| -
| |
| I Grashof Number, Gr gpATL /(gp) 143036227.2 743801381.9 14157235436 73360798959 2.32943E+11 6.05747E+11 1.2656E+12 -
| |
| I 3 3 Grashof Number, Gr6 g0AT(r0 -rj)/(i/p) 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(Gr6 Pr)'kI(ro-r,) 172.61 C =
| |
| 231.07
| |
| '
| |
| 377.74
| |
| *4 n=
| |
| 483.58
| |
| --
| |
| 560.49 607.56 617.61
| |
| '0 W/m -oC 2
| |
| I I
| |
| I I
| |
| I I
| |
| I File No.: VY-16Q-309 Page 20 of 32 I
| |
| Revision: 0 F0306-01 RO I
| |
| | |
| StructuralIntegrityAssociates, 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) Týý - Tr, AT 8.40 1200 24.00 36.00 48.00 60.00 72.00 °F
| |
| - 4.67 6.67 13.33 20.00 26.67 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-°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-°C
| |
| .............................
| |
| (Sefi ). .......................... 1. 0.998 1.010 1.030 1.080 1.190 1.5102 tu/tbm-°F 3
| |
| P 16,018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m (Density) 1 62.3 62.1 60.1 57.3 53.6 .49.0 42.4 Ibm/ftI 3 3 i* 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 -°C 3
| |
| (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
| |
| *-F 2
| |
| 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 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 (DinmcViscosity - - 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 -
| |
| FPrandtlNumber)
| |
| Calculated Parameter Formula 70 100 . 200 300 400 500 600 °F Reynold's Number, Re pVD/p 862650 1257036 2704761 4086325 5343225 6489626 6789048 -
| |
| 3 2 Grashof Number, Gr gOATL /(pJp) 230651605.4 1199409312 22829105215 1.18297E+11 3.75631E+11 9.76791E+11 2.04083E+12 3 3 Grashof Number, Grq gPAT(ro-rj) /)(pp) 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 NaturalConvection Heat TransferCoefficient:
| |
| Case: Enclosed cylinder C = 'o n 020 (see*page 9ý1of -51) 2 H+re C(GriPr)nk/(r0 -ri) 197.20 26398 431 55 552.46 640.32 694.10 70557 Wim -°c 2
| |
| : '. 34:73 4649 7600w j112.77 7 .11 :7,: A112 A . 124.26 B t/hF-f1 _-F File No.: VY-16Q-309 Page 21 of 32 Revision: 0 F0306-01 RO
| |
| | |
| -I V Structural IntegrityAssociates, Inc.
| |
| I Table 11: First Partial Heat Transfer Coefficients for Region 9 I Pipe Inside Diameter, D = . , inches = 0.665 ft 100% rated flow = 3,200 gpm Flow, % of rated-Fluid Velocity, V =
| |
| Characteristic Length, L = D =
| |
| ."I 20.522 0.665 fl/sec =
| |
| ft=
| |
| 0.203 3,200.0 0.203 m
| |
| gpm =
| |
| m 1.234236214
| |
| @T=
| |
| @
| |
| Density, p =
| |
| Mlb/hr 549 48.087 TF 3 Ibm/ft II Tflý - Ta,_, AT = assumed to be 12% of fluid temperature = 8.40 12.00 24.00 36.00 48.00 60.00 72.00 TF Note The ebove -fVno3n is basedon W With 467 667 13 33 2000 28 67 33.33 40.00 °G I
| |
| paVVv..ar*'as 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-°F CP
| |
| .(SeificHeat .
| |
| p (Density)
| |
| .1.000 4.1869 16.018 4.185 997.1 62.3 4.179 0.998 994.7 62.1 4.229 1.010 962.7 60.1.
| |
| 4.313 1.030 917.8
| |
| ,57.3 4.522 1.080 858.6 53.6 4.982 1.190 784.9 49.0 6.322 1.510 679.2 42.4 kJ/kg-°C Btu/lbm-'F kg/m3 Ibm/ft 3 3 3
| |
| I p 1.8 1.89E-04 3.24E-O4 .66E-04 1.01E-03 1.40E-03 1.98E-03 3.15E-03 m /m -'C I
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| 5 (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 -'F2 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 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..-8E-0............._7_.0O5.
| |
| .................
| |
| ......... 30E. E 951........ 05 ........... mIb
| |
| .... ..0.---0......
| |
| _5..T m s ....
| |
| I 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 -
| |
| 3 2 Grashof Number, Gr gRIATL/(Pip) 7.2279E+07 3.7586E+08 7.1540E+09 3.7071E+10 1.1771E+11 3.0610E+11 6.3954E+11 --
| |
| I 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 TransferCoefficient:
| |
| 08 0 4 2 H._= 0.023Re p r kD 11,307.23 13,480.10 19,00402 22,266.42 24,145.63 24,753.78 23,524.01 W/m -. C 2
| |
| 2,37403 ,3 8 252-38 4,359.48 4,142900 61 B1t99r3t r-ft -'F
| |
| ~48580EO3. 2 I
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| '3,841E-03~ 6.4-56E-03 7.564E-03 .8.203E03~ 28.409E-03K "7.92-03 Btu/sec-in -'F From [4J.:
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| Inside Surface Natural Convection Heat Transfer Coefficient:
| |
| Case: Enclosed cylinder C K<.5 5 ~. n= ~ ,25 G (se- pae9),39M 41 2
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| H1ftee C(GrPr)'knL 24385 346.81 62932 85534 1,03727 1,17350 1,251 33 W/m -°C 2
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| 42.94 6108 1103 I 182.68 20GA7 220.38 Btu/hr-ft -°F I
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| '-
| |
| 8,284E-05 1,178E-04' >2l381E04 ZS0,1 2 3 524E04' - 87E.O4 4.261k+ Btu/sec-in-°F U
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| I I
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| I I
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| I File No.: VY-16Q-309 Revision: 0 Page 22 of 32 I
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| F0306-01 RO
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| V StructuralIntegrityAssociates, Inc.
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| 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) T* - Tj,_ AT = 8.40 12.00 24.00 36.00 48.00 60.00 72.00 °F 4.67 .6.67 13.33 20.00 26.67 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 &.6784 0.6836 0.6611 0.6040 0.5071 W/m-°C
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| ..Theral.Conducivity) . 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-°C
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| -.. . 1.000 0.998 1.010 1.030 1.080 1.190 1.510 Btu/Ibm-°F3 p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3
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| 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 -.C 3 3 (Volumetric Rate of Expansion) 1.05E-04 1.80E-04 3.70E-04 5.60E-04 7.80E-04 1.10E-03 11.75E-03 ft /ft --F 2
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| . 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 iMns
| |
| .. avitat ional Constant) . 32.17 32.17 . 32.17 32.17 32.17 32.17 32.17 ft/s.
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| 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)
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| Calculated Parameter Formula 70 100 200 300 400 500 600 -F Reynolds Number, Re PVD/1p 862650 1257036 2704761 4086325 5343225 6489626 6789048 ---
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| 3 2 Grashof Number, Gr g0ATL /(Pilp) 230651605.4 1199409312 22829105215 1.182976211 3.75631E+11 9.76791E+11 2.04083E+12 --
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| 3 3 Grashof Number, Gr 5 gDAT(r 0-ri) /(p/p) 5.42E+05 2.82E+06. 5.37E+07 2.78E+08 8.83E+08 2.30E+09 4.80E+09 ---
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| Rayleigh Number. Ra GrPr 1609948206 5409335995 43603590961 1.44323E+11 3.56849E+11 8.39063E+11 2.18369E+12 ---
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| Rayleigh Number, Ra GrsPr 3.79E+06
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| * 1.27E+07 1.03E+08 3.39E+08 8.39E+08 1.97E+09 5.13E+09 ---
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| From [4]:
| |
| Annulus NaturalConvection Heat TransferCoefficient:
| |
| Case Enclosed cylinder C = n=
| |
| 2 H- C(GrýPr)'kJ(ro-r) 125.02 167.35 273.58 350.24 405.94 440.03 447.30 WIm -C
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| 'o 2 .
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| ý-. . 41..1 A i 77 - -'.1. 1, 77 File No.: VY-16Q-309 Page 23 of 32 Revision: 0 F0306-01 RO
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| I V StructuralIntegrity Associates, Inc.
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| I 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 I transfer coefficients (HTCj in Table 13). These are generated by "Heat Transfer Coefficients.xls".
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| I Till I
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| RTC+
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| HTCJ + 1T - )
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| TC l f) 1 TCJJJ)
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| HTCRes I
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| Where:
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| HTCRes = Resultant HTC i HTCi = HTC of it " material Ti TCi
| |
| =
| |
| =
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| Thickness of ith material Thermal Conductivity of i" material I The reference for this equation is [4].
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| I Table 13: Resultant Heat Transfer Coefficients for the Regions Material i 100% Flow
| |
| . Material I
| |
| Regions HTC I Thenl-I Conductivity, TicsTCII I-ITC111 Bnh~rt'F Btu/hr-ft-OF Thickness Iftli Conductivity, Btu/hr. Thickness Ift]
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| t,- . . .
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| S R2 3,921.42 9.8. .. 0.0268 9018 I
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| 3,921.42.......... . 002681
| |
| ...
| |
| 3,9.1 114-29..l- 10_,2_6_-__ -.1 144.04 i { . "{ 97.30
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| .3j,921.42 L00268 85.17 9.8 00.268 8.5.17 98 00304 97.30 3,921.42 3,921.42 9.8 0.0268 i 61.68 4-500 I
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| 0.2 iT Regions 14TC I STheres T ConduHvit.
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| Co utiy'
| |
| :
| |
| Thickness B (u/r-ft-or 0% Flow fITC! i.f' ThH,;
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| Conductivity, M
| |
| -
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| Btu/fidr- Thickness [ftl liTCIIl [Cs n I
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| I 142.98 150.64 _-. ........
| |
| . . ...I .. . . . . 2............ ..... . .. . ....* -..... . -2. . .... * . . . ... .......
| |
| ........ ... . .........
| |
| 98 0.0268 4.4'61 150.64 150.64
| |
| ..*.*. ~~
| |
| 9.8
| |
| ...............
| |
| ~ ~ =..
| |
| 0.0268 00268
| |
| =..........................................................
| |
| == ==== == ===
| |
| 85.17 8517
| |
| =======
| |
| 98
| |
| ===
| |
| 9 0 .0304 o -30==
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| 9730 I
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| 150.641-506 0.2 9.8 . 0 .0268 . 61. . . . . . .
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| I File No.: VY-16Q-309 Revision: 0 Page 24 of 32 I F0306-O I RO I
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| 1Structural integrityAssociates, Inc.
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| 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.
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| 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.
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| The limiting safe end location was chosen based on the highest thermal stress intensity at 100% flow.
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| Node 3719 on the inside surface of the core spray nozzle was selected for the safe end analysis and shown in Figure 6.
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| AN7 NODAL SOLUTION NODAL SOLUTION APR 27 2007 APR 27 2007 STEP=26 SUB =1 AC AN' 16:10:09 STEP=26 SUB =1 16:10:09 TIME=2.5 TIME=2.5 SINT (AVG) SINT (AVG)
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| DMX =.816948 DMX =.816948 SMN =97.958 SMN =97.958 SMX =75874 SMX =75874 Node 3719 - - Node 3737 Node 3719 -Node 3737 rr x 97.958 16937 33776 50615 67454 i15 67454 8517 25357 42196 59035 75874 8517 2535" 59035 75874.
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| Core Spray Nozzle Finite Element Model Figure 6: Safe End Critical Thermal Stress Location, Node 3719 File No.: VY-16Q-309 Page 25 of 32 Revision: 0 F0306-01R0
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| StructuralIntegrity Associates, Inc.
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| I I
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| 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 I the nozzle forging region. Therefore, this location is a reasonable choice for the limiting location.
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| I I
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| I i
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| I I
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| I U
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| Figure 7: Blend Radius Limiting Pressure Stress Location, Node 2166 I
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| I i
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| II File No.: VY-16Q-309 Revision: 0 Page 26 of 32 I F0306-O I RO I
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| IV StructuralIntegrityAssociates, Inc.
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| 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."
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| 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."
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| As the models were run with a 400'F step change in temperature, and the Green's Functions are for a I°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:
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| 0% Flow Rate:
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| SE FlowO T Green.xls SE Flow0 M+B-Green.xls BLEND FlowO M+B Green.xls BLENDFlowOTGreen.xls 100 Flow Rate:
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| 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 Page 27 of 32 Revision: 0 F0306-OI RO
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| StructuralIntegrity Associates, Inc.
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| 80000 40000 0 200 400 600 800 1000 Time (see)
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| Figure 8: Safe End Total Stress History, 100% Flow 30000 15000 V) 0 1000 2000 3000 4000 5000 6000 7000 8000 Time (sec)
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| Figure 9: Blend Radius Total Stress History, 100% Flow File No.: VY-16Q-309 Page 28 of 32 Revision: 0 F0306-OI RO
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| VStructuralIntegrity Associates, Inc.
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| 30000 15000 0 200 400 600 800 1000 Time (sec)
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| Figure 10: Safe End Total Stress History, 0% Flow 25000 20000 15000 U) 10000 5000 0 1000 2000 3000 4000 5000 6000 7000 8000 Time (sec)
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| Figure 11: Blend Radius Total Stress History, 0% Flow File No.: VY-16Q-309 Page 29 of 32 Revision: 0 F0306-01 RO
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| StructuralIntegrityAssociates, Inc.
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| I The pressure stress intensities for the safe end and blend radius paths were extracted using the ANSYS I
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| post-processing file "extractP.inp." This produced two files, SEP.OUT for the safe end and BRP.OUT for the blend radius.
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| I 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 I
| |
| the final pressure results for the safe end and blend radius.
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| I Table 14: Pressure Results (1,000 psi) I Membrane plus Total Stress Location Bending Stress Intensity Intensity (psi)
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| I Safe End (psi) 12,020 12,030 I
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| Blend Radius 34,970 35,860 I
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| Results were also extracted from the vessel portion of the model to verify the accuracy of the results I
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| 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 I
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| portion of the 2D axisymmetric model is a sphere, but the true geometry is the intersection of two cylinders. I The equation for the membrane hoop stress in a sphere is:
| |
| )
| |
| I 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, I
| |
| .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 I
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| 1.84 times higher than nominal vessel wall stress for the 2D axisymmetric model.
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| File No.: VY-16Q-309 Page 30 of 32 I
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| Revision: 0 F0306-01 RO I
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| I StructuralIntegrityAssociates, Inc.
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| * The equation for the membrane hoop stress in a cylinder is:
| |
| D 07 (-(pressure) x (radius))
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| S 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 1.84 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
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| * for representing the three-dimensional (3D) effect in a 2D axisymmetric model.*
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| File No.: VY-16Q-309 Page 31 of 32 Revision: 0 F0306-01 RO
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| V StructuralIntegrityAssociates, Inc. .
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| I
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| ==5.0 REFERENCES==
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| I
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| : 1. SI Calculation No. VY- 16Q-308, Revision 0, "Core Spray Nozzle Finite Element Model".
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| I
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| : 2. ANSYS, Release 8.1A1 (w/Service Pack 1), ANSYS, Inc., June 2004.
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| I
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| : 3. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition, 2000 Addenda.
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| : 4. J. P. Holman, "Heat Transfer," 4th Edition, McGraw-Hill, 1976.
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| : 5. J. P. Holman, "Heat Transfer," 5th Edition, 1981.
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| : 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
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| : 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.
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| I I
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| I I
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| I File No.: VY-16Q-309 Page 32 of 32 I Revision: 0 F0306-0I RO I
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| VStructuralIntegrity Associates, Inc.
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| APPENDIX A FINITE ELEMENT ANALYSIS FILES
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| ,File No.: VY-16Q-309 Page Al of A3 Revision: 0 F0306-OIRO
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| StructuralIntegrityAssociates, Inc. I I
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| i ANSYS Input Files File Name Description I 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
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| I I
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| I I
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| File No.: VY-16Q-309 Page A2 of A3 Revision: 0 F0306-01 RO I
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| V StructuralIntegrityAssociates, Inc.
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| 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,
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| _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 Page A3 of A3 Revision: 0 F0306-01 RO
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| FS't-ructural IntegrityAssociates, Inc.
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| CALCULATION PACKAGE File No.: VY- 16Q-310 Project No.: VY-16Q PROJECT NAME:
| |
| Environmental Fatigue Analysis of VYNPS CONTRACT NO.:
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| 10150394 CLIENT: PLANT:
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| 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)
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| Signature & Date Signatures & Date 0 1-27 Initial issue Terry J. Herrmann Roland Horvath/
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| 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
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| StructuralIntegrityAssociates, Inc. H
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| !
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| Table of Contents
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| . . ......... . .....
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| .0 O B JEC TIV E ..................................
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| 12... . . . . . . . . . .. .. ...
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| . ..................................................... ....4 2.0 METHODOLOGY.................................................................................... 4 3.0 AN A LY 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.
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| 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
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| I I
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| File No.: VY-16Q-310 Page 2 of 27 I Revision: 0 F0306-01 RO I
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| U Structuralintegrity Associates, Inc.
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| List of Figures Figure 1: Transient 03: Start Up.................................................................................. 23 Figure 2: Transient 11: Loss of Feedwater Pumps, Isolation Valves Close ................................ 23 Figure 3: Transient 14: Single Relief of Safety Valve Blow Down ............................................. 24 Figure 4: Transient 21-23: Shut Down Vessel Flooding .............................................................. 24 Figure 5: Transient 30: Emergency Shut Down 100% Flow (Safe End) ........................ ................. 25 Figure 6: Transient 30: Emergency Shut Down 100% Flow (Blend Radius) ....................... 25 Figure 7: External Forces and Moments on the Core Spray Nozzle ......................................... 26 Figure 8: Typical Green's Functions for Thermal Transient Stress .......................... 26 Figure 9: Typical Stress Response Using Green's Functions ........................................................ 27 File No.: VY-16Q-310 Page 3 of 27 Revision: 0 F0306-01 RO
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| | |
| StructuralIntegrityAssociates, 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.
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| 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 section.
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| I 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 refine the fatigue usage so that an environmental fatigue factor can be determined for subsequent I
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| 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 sum the stresses due to pressure, moments and through wall thermal gradient effects, regardless of I
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| 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
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| 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.
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| 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
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| 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.
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| The steps involved in the evaluation are as follows:
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| SDevelop finite element model I :Develop
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| *Develop heat transfer coefficients and boundary conditions for the finite element model Green's Functions Develop thermal transient definitions
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| *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*
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| 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 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).
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| 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 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,
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| *the real-time stress response for the input thermal transient is computed.
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| 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
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| *material properties and heat transfer coefficients. Therefore, these parameters are chosen to bound all
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| .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.
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| 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.
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| I Fatigue calculations are performed in accordance with ASME Code, Section 111, Subsection NB-.
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| 3200 methodology. Fatigue analysis is performed for the two limiting locations (one in the safe end I*File No.: VY-16Q-310 Revision: 0
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| .Page 5of 27 F0306-01 RO
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| Structuralintegrity 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.
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| 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
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| : 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.
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| 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) requiresthe following three input files:
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| I
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| * 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 to compute K, per ASME Code, Section III requirements.
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| I 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.).
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| * Input file "TRANSNTJNP": This file contains the input transient definition for all thermal transients to be analyzed for the location being evaluated.
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| 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.
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| 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. .
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| 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. .
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| 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.
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| 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.
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| 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.
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| The steps associated with this process are described in the following sub-sections.
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| 3.1 Transient Definitions (for program STRESS.EXE)
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| The program STRESS.EXE requires the following three input files for analyzing an individual transient:
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| 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%.
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| * Green.cfg is configured as described in Reference [4].
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| * 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:
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| o Transients 02, 03, 11, 14, 21-23 and 24 are run at 0% flow.
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| o Transient 30 runs at 100% flow rate per [3]. The transient of emergency shutdown is numbered as 30.
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| The remaining transients are not included in this analysis, as temperature changes from them are considered negligible to have impact on the results.
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| 3.2 Peak and Valley Points of the Stress History (for program P-V.EXE)
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| 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.
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| 3.3 Pressure Load The pressure stress associated with a 1000 psi internal pressure was determined in Reference [1].
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| I These values are as follows:
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| ,I Membrane plus Total Stress Location Bending Stress Intensity Intensity (psi) I (psi)
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| Safe End 12,020 12,030 I
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| Blend Radius 34,970 35,860 I
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| 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).
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| I The pressure stress is combined with the peak and valley points to calculate the final stress values I
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| used for fatigue analysis.
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| I 3.4 Attached Piping Loads Additionally, the piping stress intensity (stress caused by the attached piping) was determined. These I
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| piping forces and moments are determined as shown in Figure 7.
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| The following formulas are used to determine the maximum stress intensity in. the nozzle at the two I
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| 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:
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| I For Cut I:
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| (Mx) 1 = M. - FYLI (MY), =My + Fý,Lj I
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| -FL I
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| For Cut 11: (M*) 2 =MX (My)2 = My + FxL2
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| ,I I
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| I The total bending moment and shear loads are obtained using the equations below:
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| ForCut1:MI, = x/(MJ), +(MY),,
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| For CutI: 1 2 2 I FY= V(Fx) 2 + (Fý) 2 The distributed loads for a thin-walled cylinder are obtained using the equations below:
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| I N 7 IM rR N[2 RN]
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| N- F +-
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| qrRN 2RN To determine the primary stresses, PM, due to internal pressure and piping loads, the following
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| * equations are used.
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| For Cut I, using thin-walled equations:
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| PaIV Nz 2tN tN I (PM)o = Pa-NtN (PM) R -P qN TM.
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| 2 4(P SI Ior 2
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| +-i(ZM)Z 6 S 2
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| =\(jPm)z -(M)R 3 Where:
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| L, = The length from the end of the nozzle where the piping loads are applied to the location of interest in the blend radius.
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| L2 The length from the end of the nozzle where the piping loads are applied to the locationI of interest in the safe end.
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| Mxy, = The maximum bending moment in the xy plane.
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| Fyx = The maximum shear force in the xy plane..
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| NZ = The normal force per inch of circumference applied to the end of the nozzle in the z direction.
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| qN = The shear force per inch of circumference applied to the nozzle.
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| RN = The mid-wall nozzle radius.
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| Because pressure was not considered in this analysis, the equations used for Cut I are valid for Cut II.
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| In addition, the equations. can be simplified as follows:
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| (PM, =-NZ tN (PM) =0 I (PM)R =0 T-M =-q SIm*4x =2(r. )ýoi or OF(
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| S1m4x= 2 ; +(rM).° Per Reference [5], the core spray nozzle piping loads are as follows:
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| F,, = 2,500 lbs Fy 4,600 lbs F, = 1,700 lbs M, 22,000 ft-lb = 264,000 in-lb My = 7,100 ft-lb = 85,200 in-lb M= 8,800 ft-lb = 150,600 in-lb I
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| 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.
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| 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.
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| 3.5 Fatigue Analysis (for program FATIGUE.EXE)
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| 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.
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| 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:
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| Blend Radius Safe End Piping (SA508 Class II) (N06600) (Stainless Steel)
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| 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] @
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| Values, Sm 600°F 600OF 600°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]
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| The Geometric ti Stress Th etes1.0 m 4.0 See Note 1.8 [14]
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| Concentration Factor K1 Note: Conservative bounding value per ASME Code, Section NB-3600 to cover thread and weld regions.
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| 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.
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| 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].
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| The results described are contained in EXCEL files BRresults.xls and SEresults.xls, which are contained in the computer files.
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| 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.
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| I 5.0 ENVIRONMENTAL FATIGUE ANALYSIS i
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| Per Reference [7], the dissolved Oxygen (DO) calculation shows the overall HWC availability is 47%.
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| It means the pre-HWC is 53%.
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| I 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 I neglected and EAF assessment of the nozzle base material is performed.
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| For the blend radius location, the environmental fatigue factors for pre-HWC and post-HWC are I 11.14 and 8.82 from Table 4 of Reference [7]. It results in an EAF adjusted CUF of (11.14 x 53% +
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| 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.
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| I 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, I
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| which is acceptable (i.e., less than the allowable value of 1.0). The overall environmental multiplier is 1.49. I 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 I
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| multiplier is 8.36.
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| A Fatigue Environmental Multiplier of 1.49 for Ni-Cr-Fe was applied to the safe end fatigue usage and 8.36 for stainless steel to the piping. This results in the safe end being the limiting location for I
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| fatigue.
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| ==6.0 REFERENCES==
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| I SI Calculation No. VY-16Q-309, Revision 0, "Core Spray Nozzle Green's Functions."
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| 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.
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| 3 GE Certified Design Specification No. 26A6019, Revision 1, "Reactor Vessel -Extended Power Uprate," August 29, 2003, SI File No. VY-05Q-236.
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| 4 Structural Integrity Associates Calculation (Generic) No. SW-SPVF-01Q-301, Revision 0, "STRESS.EXE, P-V.EXE, and FATIGUE.EXE Software Verification."
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| S 5 VY Drawing 5920-0024, Revision 11, Sht. No. 7, "Reactor Vessel," (GE Drawing No.
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| 919D294), SI File No. VY-05Q-241.
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| 6 American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition, 2000 Addenda.
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| 7 SI Calculation No. VY- 16Q-3 03, Revision 0, '"'Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell Bottom Head."
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| 8 American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III Subsection NB, 1998 Edition, 2000 Addenda.
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| 9 NUREG/CR-6260 (INEL-95/0045), "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components," March 1995.
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| 10 GE Design Specification No. 21A1 115, Revision 4, "Vermont Yankee Reactor Pressure Vessel," October 21, 1969, SI File No. VY-05Q-210.
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| 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.
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| 12 NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," U. S. Nuclear Regulatory Commission, September 2005.
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| 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,"
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| December 1995.
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| 14 American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Subsection A, Article4, 1965 Edition with Winter 1966 Addenda.
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| File No." VY-16Q-310 Page 13 of 27 Revision: 0 F0306-01 RO
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| Table 1: Blend Radius Transients 1,2,3 Transient Number Time Temp Time Step
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| (*fs)
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| Pressure
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| {
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| Flow Rate (GPM)
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| I
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| : 2. Design HYD Test 100 0 I
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| -- --
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| 1100 120 Cycles 50
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| : 3. Startup 0 100 0 0 300 Cycles
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| : 11. Loss of Feedwater 16164 24164 0
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| 549 549 526 16164 8000 1010 1010 1010 (0%)
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| 0 I
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| Pumps 10 Cycles 13 233 3 526 526 300 3
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| 10 220 1190 1135 1135 (0%)
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| I 2213 500 1980 1135 2393 6893 7313 300 500 300 180 4500 420 885 1135 675 I
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| 7613 11213 16577 300 400 549 300 3600 5364 675 240 1010 I
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| 16637 549 60 1010 16638 16698 542 542 60 1 1010 1010 I
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| 16699 526 1 1010
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| : 14. SRV Blowdown I Cycle 24699 600 0
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| . 526 526 375 8000 600 1010 1010 400 0
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| (0%)
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| I I
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| 11580 70 10980 50 19580 70 8000 50 21-23. Shutdown 0 549 1010 0 300 Cycles 6264 375 .6264 50 (0%)
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| 6864 16224 24224 330 100 100 600 9360 8000 50 50 50 I
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| I
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| : 24. Hydrostatic Test -- 100 -- 50 1 Cycle 1563 50
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| : 30. Emergency Shut Down 0 549 1010 3200 I Cycle 10 11 8011 406 70 70 10 1
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| 8000 250 250 0
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| (100%)
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| -j I
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| Note:
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| : 1. Instant temperature change is I sec.
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| I
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| : 2. This is due to the length of the Green's Function; The transients are plotted using an 8000 second steady 3.
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| state increment.
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| The number of cycles for 60 years is from Reference [2]. I I
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| I-3 Table 2: Safe End Transients",2,'
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| Transient Time Temp Time Step Pressure Number f F) Ls) (s)sfs§q)
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| : 2. Design HYD Test 100 -- 0 120 Cycles 1100 50
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| : 3. Startup 0 100 0 300 Cycles 16164 549 16164 1010 17164 549 1000 1010
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| : 11. Loss of Feedwater 0 526 1010 Pumps 3 526 3 1190 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 17699 526 1000 1010.
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| : 14. SRV Blowdown 0 526 1010 0 1 Cycle 600 375 600 400 (0%)
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| 11580 70 10980 50 12580 70 1000 50 21-23. Shutdown 0 549 1010 0 300 Cycles 6264 375 6264 50 (0%)
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| 6864 330 600 50 16224 100 9360 50 17224 100 1000 50
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| : 12. Hydrostatic Test --- 100 50 1 cycle 1563 50
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| : 30. Emergency Shut Down 0 549 1010 3200 1 Cycle 10 406 10 250 (100%)
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| 11 70 1 250 1011 70 1000 0 Note:
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| I. Instant temperature change is 1 sec.
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| : 2. The transients are plotted using a 1000 second steady state increment. The difference is due to the length of the Green's Function for the safe end.
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| : 3. The number of cycles for 60 years is from Reference [2].
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| I Table 3: Maximum Piping Stress Intensity Calculations for Blend Radius Blend Radius External Pipinq Loads I
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| kips kips I
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| Fz=
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| Mx=
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| Kips in-kips I my= in-kips Mz-OD=
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| in-kips in I
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| ID= in RN --
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| L =
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| 7.65 in
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| ________in I
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| tN =
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| (Mx)2 3.56 22.24 in in-kips I
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| (MY)2 162.24 in-kips MxV =
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| FxY =
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| 203.14 5.24 in-kips kips I
| |
| Nz=
| |
| N 1.14
| |
| -0.07 kips/in kips/in I
| |
| Primary Membrane Stress Intensity PMz
| |
| =
| |
| 0.32
| |
| -0.02 ksi ksi I
| |
| SImax Si[max 0.32 322.52 1 ksi psi.
| |
| I 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
| |
| File No.: VY-16Q-310 Revision: 0 Page 16 of 27 I F0306-O1RO I
| |
| | |
| V StructuralIntegrityAssociates, Inc.
| |
| Table 4: Maximum Piping Stress Intensity Calculations for Safe End Safe End External Piping Loads Parameters Fx = F0 , kips Fz = 4,(*40 kips Fz ý ' 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] for safe end and blend radius paths, respectively.
| |
| File No.: VY-16Q-310 Page 17 of 27 Revision: 0 F0306-01RO
| |
| | |
| StructuralIntegrity Associates, Inc. I Table 5: Blend Radius Stress Summary I
| |
| 1 I
| |
| 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:
| |
| 3
| |
| ___________
| |
| ___0
| |
| ____100
| |
| ___100 23700 12600 _ _
| |
| 100 100 _
| |
| ___
| |
| _
| |
| 1100 50 0 ____0 0 ___0 39446 1793
| |
| ____0 ___
| |
| 38467 ____19 1749 _ _ 19 0 ___19 19 19 19 19.
| |
| 19 19 39465 __
| |
| ___
| |
| 1812 ___1768 23719 ___12619 19 38486 120 120 120 300 I
| |
| 24164 2100 549 1010 36219 35320 306 306 38625 ___38806 300 I
| |
| _3180 ___
| |
| 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.
| |
| I 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 1 TO__
| |
| 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 14 21-23 24699 19580 0
| |
| 0 3209 3209 25122.
| |
| 2103 364,4____526 3644 ___
| |
| 13197 _ __
| |
| 3161 526 70 ____50 549[ 1010 1010 1010 36219 36219 1793 36219 35320 ___291 35320.__ 291
| |
| ___1749 35320
| |
| _ _
| |
| 306 0 __
| |
| 291 291 306 0
| |
| _ 39719 39719.___ 39255 26915 38628 39255 149461 38787
| |
| _ _ 10 300 1___
| |
| I
| |
| ____ 24224 23680 12568 -100 _ __50. :1793 1749 _ __19 19 25492 14336 300 24 300
| |
| ____
| |
| _____100
| |
| ___
| |
| 2040
| |
| ___100 2950
| |
| ____50 100 ____50 549 1563 1010, 1793 56049 1793 362191 1749 54658 1749 35320
| |
| ____19
| |
| ____19 19 3061 19 19 19 3061 1812 56068 1812 38565
| |
| ____1768 54677 1768 385761 1
| |
| 1 1
| |
| 11 I
| |
| I
| |
| ____ 8011, 25700, 149001 701 :
| |
| of__ 0 0 ___ 0 ____ 01 257001 149001 11 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.
| |
| I 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°F)/(575°F -70'F).
| |
| I 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).
| |
| I Column 13: Number of cycles for the transient (60 years).
| |
| I I
| |
| I I
| |
| I File No.: VY-16Q-310 Revision: 0 Page 18 of 27 I F0306-01 RO I
| |
| | |
| V StructuralIntegrity 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 6802 8 10236 526 1190 14316 14304 6276 _. : 6276 ___ 29393 30815 _ 10 13 8802 10236 526 1135 l 13654
| |
| .3 13643 6276 .6276 ___ 28732 ____ 30154 _ : . 10 164 1_______ 11645 11598 408 1135 13654 13643 ___ 4657 4657 ___ 29956 _ 29898 _ 10 672 4808 5791 344 1135 13654 136ý43 __ 3775 3775 ___ 22237 :____ 23209 , 10
| |
| _.__.________ 2374 11140 10841 361 912 10971 10962 ___ 4005 4005 ___ 26116 _;:-_:25808 __;= 10
| |
| ;-29554722 5577 325 916 11019 1.1010 3509 3509 __;19250 ____ 20096 ____ 10 7054 9518 10162 _._.__ 441 959 11537 1*1527 ___ 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 1010 0 12150 299549 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
| |
| :1385600 44694 162 250 3002 30001 1260 1260 89862 48953 ______ 1
| |
| ____ 1011 -1? -101 70 0 01 0___'
| |
| _ 0 ____0 -12 -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°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 Page 19 of 27 Revision: 0 F0306-0I RO
| |
| | |
| StructuralIntegrity Associates, Inc.
| |
| I I
| |
| 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 I
| |
| n .2 Sm = 26700. psi Ecurve = 3.000E+07 psi Eanalysis = 2.670E+07 psi Kt = 1.00 I
| |
| MAX 56068.
| |
| 51325.
| |
| MIN 19.
| |
| 19.
| |
| RANGE 56049.
| |
| 51306.
| |
| MEM+BEND 54658.
| |
| 45212.
| |
| Ke 1.000 1.000 Salt 31488.
| |
| 28824.
| |
| Napplied 1.OOOE+00 1.OOOE01 Nallowed 1.896E+04 2.501E+04 U
| |
| .0001
| |
| .0004 I
| |
| 46174. 19. 46155. 45531. 1.000 25930. 1.OOOE+01 3.460E+04 .0003 46013.
| |
| .45991.
| |
| 44605.
| |
| 39899.
| |
| 19.
| |
| 19.
| |
| 19.
| |
| 19.
| |
| 45994.
| |
| 45972.
| |
| 44586.
| |
| 39880.
| |
| 43180.
| |
| 41149.
| |
| 39443.
| |
| 39707.
| |
| 1.000 1.000 1.000 1.000 25839.
| |
| 25827.
| |
| 25048.
| |
| 22404.
| |
| 1.OOOE+01 1.OOOE+01 1.00E++/-01 1.OOOE+01 3.498E+04 3.503E+04 3.848E+04 5.695E+04
| |
| .0003
| |
| .0003
| |
| .0003
| |
| .0002 I
| |
| 39719. 19. 39700. 39236. 1.000 22303. 1.000E+01 5.824E+04 .0002 39719.
| |
| 39719.
| |
| 39465.
| |
| 39465.
| |
| 19.
| |
| 19.
| |
| 19.
| |
| 1812.
| |
| 39700.
| |
| 39700.
| |
| 39446.
| |
| 37653.
| |
| 39236.
| |
| 39236.
| |
| 38467.
| |
| 36718.
| |
| 1.000 1.000 1.000 1.000
| |
| :22303.
| |
| 22303.
| |
| 22161.
| |
| 21153.
| |
| 1.OOOE+01 5.824E+04 1.OOOE+00 5.824E+04 3;800E+01.6.012E+04 8.200E+01 7.572E+04
| |
| .0002
| |
| .0000
| |
| .0006
| |
| .0011 I
| |
| 39292. 1812. 37480. 38223. 1.000 21056. 1.OOOE+01 7.747E+04 .0001 38628.
| |
| 38628.
| |
| 38628.
| |
| 38628.
| |
| 1812.
| |
| 1812.
| |
| 1812.
| |
| 23719.
| |
| 36816.
| |
| 36816.
| |
| 36816.
| |
| 14909.
| |
| 37019.
| |
| 37019.
| |
| 37019.
| |
| 26168.
| |
| 1.000 1.000 1.000 1.000 20683.
| |
| 20683.
| |
| 20683.
| |
| 8376.
| |
| 2.800E+01 8.466E+04 1.OOOE+00 8.466E+04 1.OOOE+00 8.466E+04 2.700E+02 5.366E+07
| |
| .0003
| |
| .0000
| |
| .0000
| |
| .0000 I
| |
| 38625. 23719. 14906. 26187. 1.000 8374. 3.OOOE+01 5.375E+07 .0000 I
| |
| 38625. 25492. 13133. 24470. 1.000 7378. 2.700E+02 3.042E+08 .0000 38565. 25492. 13073. 24240. 1.000 7344. 1*000E+00 3.374E+08 .0000 35265. 25492. 9773. 14585. 1.000 5490. 1.OOOE+01 1.OOOE+20 .0000
| |
| .26915. 25492. 1423. 610. 1.000 799. i.OOOE+00 1.OOOE+20 .0000 25700. 25492. 208. 564. 1.000 117. 1.OOE+00 1.000E+20 .0000 TOTAL USAGE FACTOR .0043 I
| |
| I I
| |
| I I
| |
| I I
| |
| I File No.: VY-16Q-310 Revision: 0 Page 20 of 27 I F0306-01 RO I
| |
| | |
| 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 MIN RANGE MEM+BEND Ke Salt Napplied Nallowed U 89862. -12. 89874. 48963. 1.000 112423. 1. OOOE+00 1. 213E+03 .0008 29956. 413. 29543. 29485. 1.000 56029. 1.00OE+OI 1. 910E+04 .0005 29393. 413. 28980. 30402. 1.000 57068. 1.OOOE+01 1. 746E+04 .0006 28732. 413. 28319. 29741. 1.000 55813. 1.OOOE+01 1. 946E+04 .0005 28386. 413. 27973. 29119. 1.000 54762. 1.OOOE+01 2. 140E+04 .0005 28022. 413. 27609. 29119. 1.000 54590. 1. OOOE+00 2. 174E+04 .0000 27984. 413. 27571. 18319. 1.000 39187. 7. 900E+01 1.244E+05 .0006 27984. 693. 27291. 18036. 1.000 38651. 1. OOOE+00 1.341E+05 .0000 27984. 1014. 26970. 17718. 1.000 38045. 1. 200E+02 1.460E+05 .0008 27984. 1014. 26970. 17718. 1.000 38045. 1. OOOE+00 1.460E+05 .0000 27984. 1014. 26970. 17718. 1.000 38045. 1. ooE+00 1.460E+05 .0000 27984. 1074. 26910. 17560. 1.000 37792. 9. 800E+01 1. 514E+05 .0006 27982. 1074. 26908. 28260. 1.000 53033. 2.020E+02 2. 517E+04 .0080 27982. 1678. 26304. 28418. 1.000 52971. 9. 800E+01 2. 532E+04 .0039 27228. 1678. 25550. 27638. 1.000 51502. 1. OOOE+OI 2. 919E+04 .0003 27228. 1678. 25550. 27638. 1.000 51502. 1. OOOE+01 2. 919E+04 .0003 27228. 1678. 25550. 27638. 1.000 51502. 1. OOOE+00 2. 919E+04 .0000 26155. 1678. 24477. 25775. 1.000 48339. 1 OOOE+01 4.021E+04 .0002 26116. 1678. 24438. 24794. 1.000 46923. 1.OOOE+01 4. 673E+04 .0002 25664. 1678. 23986. 25713. 1.000 48017. 1. OOOE+00 4. 159E+04 .0000 22237. 1678. 20559. 22195. 1.000 41379. 1.OOOE+01 9. 257E+04 .0001 19250. 1678. 17572. 19082. 1.000 35526. 1.OOOE+01 2. 135E+05 .0000 19216. 1678. 17538. 18186. 1.000 34234. 1. OOOE+00 2. 691E+05 .0000 15441. 1678. 13763. 15205. 1.000 28195. 1. OOOE+01 1-001E+06 .0000 13646. 1678. 11968. 12621. 1.000 23661. 1. 200E+02 1.772E+06 .0001 TOTAL USAGE FACTOR .0184 File No.: VY-16Q-310 Page 21 of 27 Revision: 0 F0306-01 RO
| |
| | |
| I V StructuralIntegrity Associates, Inc.
| |
| I Table 9: Fatigue Results for Stainless Steel Piping (60 Years)
| |
| LOCATION =
| |
| FATIGUE CURVE =
| |
| LOCATION NO. 1 -- SS Piping 2 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL)
| |
| I m= 1.7 n=
| |
| Sm =
| |
| Ecurve =
| |
| Eanalysis =
| |
| .3 17000. psi 2.830E+07 psi 2.700E+07 psi I
| |
| Kt =,1.80 MAX 89862.
| |
| MIN
| |
| -12.
| |
| RANGE 89874.
| |
| MEM+BEND 48963.
| |
| Ke 1.000 Salt 67629.
| |
| Napplied 1.O00E+00 Nallowed 8.006E+03 U
| |
| .00001 I
| |
| 29956. 413. 29543. 29485. 1.000 27845. 1.000E+01 1. 042E+06 .0000 I
| |
| 29393. 413. 28980. 30402. 1.000 27934. 1.000E+01 1.031E+06 .0000 28732. 413. 28319. 29741. 1.000 27310. 1.OOOE+01 1.11OE+06 .0000 28386. 413. 27973. 29119. 1.000 26868. 1.OOOE+01 1.171E+06 .0000 28022. 413. 27609. 29119. 1.000 26678. 1.OOOE+00 1. 198E+06 .0000 27984. 413. 27571. 18319. 1.000 22130. 7. 900E+01 2. 272E+06 .0000 I
| |
| 27984. 693. 27291. 18036. 1.000 21864. 1.000E+00 2. 392E+06 .0000 27984. 1014. 26970. 17718. 1.000 21563. 1.200E+02 2. 539E+06 .0000 27984. 1014. 26970. 17718. 1.000 21563. 1. OOOE+00 2. 539E+06
| |
| .0000 27984. 1014. 26970. 17718. 1.000 21563. 1. 000E+00 2.539E+06 27984. 1074. 26910. 17560. 1.000 21465. 9. 800E+01 2. 588E+06 ..0000
| |
| .0000 I
| |
| 27982. 1074. 26908. 28260. 1.000 25950. 2.020E+02 1.311E+06 .0002 27982. 1678. 26304. 28418. 1.000 25700. 9.800E+01 1.354E+06 .0001 27228. 1678. 25550. 27638. 1.000 24978. 1.000E+01 1.485E+06 .0000 27228. 1678. 25550. 27638. 1.000 24978. 1.000E+01 1. 485E+06 .0000 27228. 1678. 25550. 27638. 1.000 24978. 1.OOOE+00 1.485E+06 .0000 1678. .0000 I
| |
| 26155. 24477. 25775. 1.000 23634. 1.000E+01 1.779E+06 26116. 1678. 24438. 24794. 1.000 23202. 1.000E+01 1.889E+06 .0000 25664. 1678. 23986. 25713. 1.000 23351. 1.00E+00 1.850E+06 .0000 22237. 1678. 20559. 22195. 1.000 20080. 1.OOOE+01 3.442E+06 .0000 19250. 1678. 17572. 19082. 1.000 17209. 1.000E+01 7.481E+06 .0000 19216. 1678. 17538. 18186. 1.000 16816. I .O00E+00 8.600E+06 .0000 15441.
| |
| 13646.
| |
| 1678.
| |
| 1678.
| |
| 13763.
| |
| 11968.
| |
| 15205.
| |
| 12621.
| |
| 1.000 1.000 13588.
| |
| 11564.
| |
| 1.OOOE+01 1.200E+02 1.000E+20 1.000E+20 TOTAL USAGE FACTOR
| |
| .0000
| |
| .0000
| |
| .0005 I
| |
| I I
| |
| I I
| |
| I U
| |
| I File No.: VY-16Q-3 10 Revision: 0 Page 22 of 27 I F0306-01 RO I
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| | |
| StructuralIntegrityAssociates, Inc.
| |
| - Temp (F) - -Pressure (psig) 600* 1100
| |
| ~1000 1050 950 500 900 850 800 750 4'00 - 700
| |
| &.0, .650 --
| |
| 6500 30 Q..
| |
| .e - 6500 00 5050 I- - 400 050 3 200 300
| |
| -250
| |
| .0e -200 1150 100
| |
| -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 400-960 920 0
| |
| ~880 400 840
| |
| / 800 S5 760
| |
| /57200-680 200/ 6440
| |
| " 600 E 60
| |
| ." 520 480 200 440 2400 360 320 280 100 240 200 160 120 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 StructuralIntegrityAssociates, Inc.
| |
| I 600 I-Temp (-F) - - Pressure (psig)
| |
| *.1100 I
| |
| - 1050 500 1000
| |
| -950.
| |
| -900 I
| |
| -850
| |
| -800
| |
| - 750
| |
| - 700 I
| |
| -650
| |
| -600
| |
| - 550
| |
| -500 sa I
| |
| E
| |
| -450 I
| |
| i-400 200 "-
| |
| -350
| |
| -300
| |
| -250 100
| |
| -200
| |
| - 150
| |
| -100 I
| |
| I
| |
| -50 0 1000 2000 .3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 Time (seconds)
| |
| Figure 3: Transient 14: Single Relief of Safety Valve Blow Down I 600 -
| |
| I-Temp (°F) - - Pressure (psig)}
| |
| 1100 I
| |
| 1000 500-900 I
| |
| I 800 400 700 I
| |
| -600
| |
| -a 300
| |
| - 500 I
| |
| 400 200 300 I
| |
| -200 100
| |
| . 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 F0306-OI RO I
| |
| | |
| V StructuralIntegrity Associates, Inc.
| |
| -Temp (°F) - - Pressure (psig)]
| |
| 600 1100 1000 900 800 400 700 600 300 500 I- a,-
| |
| 400 200 300 200 100 100 0
| |
| 0 100 200 300 400 500 Time (seconds)
| |
| Figure 5: Transient 30: Emergency Shut Down 100% Flow (Safe End)
| |
| I- Temp (*F) - - Pressure (psig) I 600 1100 1000 500-900 800 400 700 600 300 500 400 200 300 200 100 100 0 -0
| |
| .0 1000 2000 3000 4000 5000 Time (seconds)
| |
| Figure 6: Transient 30: Emergency Shut Down 100% Flow (Blend Radius)
| |
| File No.: VY-16Q-310 Page 25 of 27 Revision: 0 F0306-OI RO
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| CStructuralIntegrityAssociates, Inc.
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| Figure 7: External Forces and Moments on the Core Spray Nozzle 0)
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| 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).
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| File No.: VY-16Q-310 Page 26 of 27 Revision: 0 F0306-O1RO
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| StructuralIntegrity Associates, Inc.
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| I CA 30O~
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| I *.. .50 ... - t ip
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| -25 sup~
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| -is SliP 200" 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 Page 27 of 27 Revision: 0 F0306-01 RO
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| V StructuralIntegrityAssociates, Inc.
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| APPENDIX A INPUT AND OUTPUT FILES File No.: VY-16Q-310 Page Al of A2 Revision: 0 F0306-OIRO
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| IStructural IntegrityAssociates, Inc.
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| 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 Page A2 of A2 Revision: 0 F0306-01 RO
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| IIJSt StrucuralIntegrity cuaI~tg~ Ass ,ooe,-
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| ociatesi Inc.
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| File No.: VY-16Q-3 11
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| - - NECH-IH14 CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME:
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| Environmental Fatigue Analysis of VYNPS CONTRACT NO.:
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| 10150394 CLIENT: PLANT:
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| Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE:
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| Feedwater Class I Piping Fatigue Analysis Document Affected Project Manager Preparer(s) &
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| Revision Pages Revision Description Approval Checker(s)
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| 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
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| V StructuralIntegrity Associates, Inc.
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| I Table of Contents
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| ,I 1.0 2.0 O B JEC T IVE ... ....
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| *. .......................................................................................................................
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| METH O D O LO G Y .................................. ...................... .............................................. ............... 3 3
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| I 3.0 ASSUMPTIONS/DESIGN INPUT .................................................. 11 4.0 5.0 A N A LY SIS... ....................................................................... ......................................................
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| RESU LTS OF AN A LY SIS .......................................................................................................
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| 14 16 I
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| 6.0 RE FEREN C E S ............................................................................................................................
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| APPENDIX A PIPESTRESS INPUT FILE ("FWHPCI.FRE")......... ...........................
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| 17 Al I
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| APPENDIX B PIPESTRESS OUTPUT FILE ("FWFHPCI.PRF") .................................................... BI List of Tables I
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| Table 1: Thermal Cycle Definitions for Feedwater Line ............................................................... 4 I Table 2: Material Properties for Feedwater System Class 1 Piping [2 App. E, 5] ......................... 12 Table 3: Feedwater/HPCI Piping Size linformation [2] ...............................
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| Table 4: Thermal Cycle Load Cases ................................... ..........................................................
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| 13 15 I
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| I List of Figures I
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| Figure 1: Feedwater/HPCI Piping from Anchor HD-36 to RPV Nozzles N-4A and N-4B ....... 10 I
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| I I
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| I I
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| File No.: VY-16Q-311 Page 2 of 17 Revision: 0 F0306-01RO I
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| * ~Structural Integrity Associates, Inc.
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| 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.
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| * 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.
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| I 2.0 METHODOLOGY The Class 1 Loop A feedwater piping system line extending from anchor HD-36 to reactor 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:
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| : 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.
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| * 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.
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| : 3. The transients defined in this calculation are the bounding set for the two loops.
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| The operating conditioris for the Class 1 portion of the feedwater line were defined based on References
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| [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.
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| 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.
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| File No.: VY-16Q-311 Page 3 of 17 Revision: 0 F0306-01RO
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| StructuralIntegrity Associates, Inc.
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| I Table 1: Thermal Cycle Definitions for Feedwater Line I
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| Thermal Conditions (2) Pressure Conditions No.
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| Transient Description (1) Piping 0per. Temp. T, Ta-t Time Rate T.- 0o-4 Pinit Pfinal of 0
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| Cycle Region (3) .(IF) ( 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 100 70 100 1800 60 85 0 1 150.0 0.0 50 .
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| Design Hydrotest (teak 11 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.
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| 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 610 100 150 100 0 STEP 125. 15 1/2 . 688.5 1010.0 1010 IV 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 260 0 STEP 180 0 1 150.0 1010.0 1010 Turbine Roll & Increase to H 260 100 180 0 STEP 140 0 1 150.0 1010.0 1010 Rated Power2(+) Rb . 180 100 ofeesalrcms I1820 (Includes 10 SCRAS4. Loss 11 100 260 0 STEP 180 01 1377.0 1010.0 1010 9 100 100 100 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 260 392 1800 264 326 100 1 9180.0 1010.0 1010 Turbine Roll & Increase to 392 te RolIýo 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 Reactor Overpressure,228 OtherSCRAMS and 60
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| "
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| 1In IVa V.
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| 392 392 392 260 260 260 392 392 392 1800 1800 1800 264 264 264 326 326 326 100 100 100 1
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| 1/2 1/2 9180.0 4590.0 4590.0 1010.0 1010.0 1010.0 1010 1010 1010 599 I
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| 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
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| : 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 tno500/ 11 100 100 100 1800 0 100 0 1 150.0 50.0 50
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| .280 1800 -224 336 50 1 45900 1010.0 1010 2000 P9scer 111 280 392 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
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| _ _ __9_280__ 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.
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| File No.: VY-16Q-311 Page 4 of 17 f Revision: 0 F0306-O1R0 I
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| *. jiStructuralIntegrityAssociates, Inc.
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| I Transient Table 1: Thermal Cycle Definitions for Feedwater Line (continued)
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| Description (1) Pipin Ope. Temp. T TL.
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| Thermal Conditions (2)
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| Time Rate T.,. Flo.
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| Pressure Conditions Pint Pfinal No.
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| of Cycle Region (3) (°F) ('F) (*F) (see-) ('F/br) (F) (%) Ratio (gpm)(4). (psi-) (psig) Cycles (I)
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| I t0 Weekly Reduction to 50%
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| l 1
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| -la fIb 11 "t0 392 392 246 100 280 280 190 l0 28 100 392 392 246 392 100 1800 1800 1800 1800 1800 224 224 112 22 0
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| 336 336 218 336 100 50 0
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| 0 50 0
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| 1 1
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| I
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| ]
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| 1 4590.0 150.0 150.0 4590.0 150.0 1010.0 1010.0 1010.0 100.0 50.0 1010 1010 1010 500 so0 2000 Power(+) IV 392 280 392 1800 224 336 50 1/2 2295.0 1010.0 I
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| 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 I 11 Turbine Trip I (-)
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| (Includes 10 Loss of .
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| Feedsster Hester Turbine Trip. ad 300 Redctio 0J Power)
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| T IV 9ib 10 Va IVb
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| ]
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| 182.5 JO0 265 265 265 265 246 100 392 392 392 392 182.5 1O0 265 265 265 265 1800
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| )800 1800 1800 1800 1800
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| -127 0
| |
| -254
| |
| .254
| |
| .254
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| -254 214 100 329 329 329 329
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| .50 0
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| 0 50 50 50 1
| |
| 1 1
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| 1/2 1/2 112 150.0 150.0 4590.0 2295.0 2295.0 2295.0 10100 50.0 1010.0 1010.0 1010.0 1010.0 1010 50 1010 1010 1010 1010 310 I .ossof Feedwater Heater, V
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| 1 lHa Ill 265 90 90 95 100I
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| . 392 265 265 182.5 100 265 90 90 95 100 1800 360 360 360 360
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| -254.
| |
| -1750
| |
| -1750
| |
| -875 0.
| |
| .
| |
| 329 178 178 139 100 50 15 0
| |
| 0 0
| |
| 1/2 1
| |
| 1 I
| |
| 1 2295.0 1377.0 150.0 150.0 150.0 1010.0 1010.0 1010.0 1010.0 50.
| |
| 1010 1010 1010 1010 50 12 Turbine Trip 2(-) 111 IV 90 90 265 265 90 90 360 360 -1750
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| -1750 . 178 178 15 15 1 1/2 1377.0 688.5 1010.0 1010.0 1010 1010 10 I IVa 1Vb V
| |
| 1 90 90 90 265 265 265 265 90 90 90 90 265 360 360 360 900
| |
| -1750
| |
| -1750
| |
| -1750 700 178 178 178 178 15 15 15 15 1/2 1/2 1/2 1-688.5 688.5 688.5 1377.0 1010.0 1010.0 1010.0 1010.0 1010 1010 1010 1010 1
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| I 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 + 11 1Heter 392 265 392 180 2540 329 100 1 9180.0 1010.0 1010 70 IV 392 265 392 180 2540 IVa 392 265 392 180 2540 329 329 100 100 1/2 1/2 4590.0 4590.0 1010.0 1010.0 1010 Va 392 265 392 ]80 2540 329 100 1/2 . 4590.0 1010.0 1010
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| !Vb 392 265 392 180 2540 329 100 1/2 4590.0 1010.0 1010
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| *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
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| * 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
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| * 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 I V )OO 275 100 900 -700 188 3 /2 1377 1010.0 1010 U For notes, see last page of table.
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| File No.: VY-16Q-311 Page 5 of 17 I Revision: 0 F0306-01 RO
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| VStructural Integrity Associates, Inc.
| |
| I Table 1: Thermal Cycle Definitions for Feedwater Line (continued)
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| Transient Cycle Description(1) Piping Region (3)y 1
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| Oper.Temp.
| |
| (F) 265 T,
| |
| (,F) 265 Tý,
| |
| 0
| |
| ( F) 265
| |
| 'Thermal Conditions (2)
| |
| Time
| |
| . (se) 0 Rate (rF/hr)
| |
| STEP T_,
| |
| (IF) 265 Fs
| |
| (
| |
| 0 Ra.,
| |
| 1 (gpm)(4) 200.0 iPressure Conditions Plait (psig) 1010.0 Pfinal..
| |
| (psig) 1010 No.
| |
| of Cyces () I 1a 265 265 265 0 STEP . 265 0 1 150.0 1010.0 1010 19 Hot Standby1(+) .
| |
| 0b
| |
| * aI IV Iva 182.5 100 265 265 323 182.5 100 265 265 265
| |
| [82.5 100 265 265 323 0
| |
| 0 0
| |
| .0 0
| |
| SuEP STEP STEP STEP STEP 183 100 265 265 294 0
| |
| 0 0
| |
| 0 0
| |
| 1 1
| |
| 1 1/21 1/2 150.0 150.0 2000 100.0 100.0 1010.0 50.0 1010.0 1010.0 1010.0 1010 50 1010 1010 1010 300 I 1Vb 0 1010.0 1010 3
| |
| 382 265 382 0 STEP 324 1/2 100.0 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 I
| |
| 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 21 Hot Standby 3(-)
| |
| Ha
| |
| /O 1
| |
| 11 IV
| |
| ]so 125 100 150 150 265 182.5 100 265 265 150 125 100
| |
| .150 150 4140 4140 0
| |
| 4140 4140
| |
| -100
| |
| -50 0
| |
| -100.
| |
| -100
| |
| -
| |
| 208 154 100 208 208
| |
| .
| |
| 0 0
| |
| 0 0 1 1
| |
| 1 1
| |
| 1/2 150.0 150.0 150.0 200.0 100.0 1010.0 1010.0
| |
| .50.0 1010.0
| |
| . 1010.0 1010 1010 50 1010 1010 300 I
| |
| IVa 283 360 203 4140 -67 322 0 1/2 100.0 1010.0 1010 I
| |
| .
| |
| 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 I
| |
| 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 U
| |
| 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 IVb V
| |
| 1 Ila 210 270 330 100 100 225 300 375
| |
| .150*
| |
| 150
| |
| . 210 270 330 100 100 600 600 600 8280 8280
| |
| -90
| |
| -100
| |
| -270
| |
| -22
| |
| * -22 218 285 353 125 125 0
| |
| 0 0
| |
| 0 0
| |
| 1/2 1/2 1/2 1
| |
| I 100.0 100.0 100.0 200.0 150.0 170.0 170.0 170.0 88.0 88.0 08 88 08 50 50 I
| |
| Oh 100 125 100 8280 . -11 113 0 1 150.0 88.0 50 24 Shutdown 3 (-) 13 IV Iva 1Vb 1* 100 100 l O0 100 100 100 150 150 210 270 100 100 100 100 100 8200 8280 8280 8280 8280
| |
| -22
| |
| -22
| |
| -40
| |
| -74 0 100 125 125 155 185 0
| |
| 0 0
| |
| 0 0
| |
| 1 I
| |
| 1/2 1/2 1/2 150.0 200.0 100.0 100.0 100.0 50.0 80.0 80.0 88.0 08.0 50 50 50 50 50 300 I
| |
| I 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 I
| |
| 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 so 392 50 0. STEP 221 40 .1 3672.0 1190.0 1135 IDa 50 392 50 0 STEP 221 40 3672.0 1190.0 1135 26 SCRAM, Loss of Feedwater Pumps 2 (-)
| |
| (First HPCI) l13 IV Iva 50 50 50.
| |
| 50 50 246 100 392 392 450 50 50 50 50 50 0
| |
| 0 0
| |
| 0 0
| |
| STEP STEP STEP STEP STEP 148 75 221 221 250 40 40 40 40 3672.0 3672.0 3672.0 12 1836.0 1/2 1836.0 1190.0 50.0 1190.0 1190.0 1190.0 1135 1135 1135 1135 1135 10 I 40.
| |
| 0 I
| |
| IVb 50 507 50 STEP 279 40 1/2 1836.0 1190.0 1135 V 50 565 1 50 0 STEP 308 40 1/2 1836.0 1190.0 1135 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)
| |
| "Vb M0 Iv IVa V
| |
| 150 150 247 343 440 50 50 50 50 50 150 247 247 343 440 1 1380 1380 1380 1380 1380 261 261 514 764 1017 100 149 149 197 245 0
| |
| 0 0
| |
| 0 10 1
| |
| 1/2 1/2 1/2 1/2 200.0 100.0 100.0 100.0 100.0 1135.0 1135.0 1135.0 1135.0 11350 1 1135 1135 1135 1135 1135 1 1l I
| |
| For notes,. see last page of table.
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| File No.: VY-16Q-3 11 Page 6 of 17 I Revision: 0 F0306-01RO I
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| S3StructuralIntegrityAssociates, Inc.
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| 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
| |
| .50 1a 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 50o 150 50 0 STEP 100 30 1/2 1377.0 1135.0 885 IVN 50 2880 50 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 Feedstbeýr 1 100 100 100 0 STEP 100 0 1 150.0 50.0 50 7
| |
| Pumps (+) 1 150 150 I50 0 STEP 150 0 1 200.0 1069.0 1135 N 150 150 I 150 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 ofFfedstez1 13 100 50 100 300 600 75 0 1 150.0 675.0 50 33 150 3pM 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 1350 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 SCRAM, SRV Blosdov 35 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 50 300 17b 275 300 900 -700 138 *3 1/2 137.7 885.0 50 U V 100 275 100 900 -700 . 188 3 1/2 137.7 885.0 50 For notes, see last page of table.
| |
| m FiRe No.: VY-16Q-311 Revision: 0 Page 7 of 17 F0306-O1 RO
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| StructuralIntegrity Associates, Inc.
| |
| Table 1: Thermal Cycle Definitions for Feedwater Line (continued~
| |
| I I
| |
| ._Thermal Conditions (2) Pressure Conditions No.
| |
| Transient Description (1) Piping Ope0. Temp. Tý Tý,. Time Rate T,, Fo0 Pinit Pfinal of 0 5 5 Cycle Region (3) ( F) (*F) (*F) (sec.). ( F/hr) ( 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 I
| |
| 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 (+) 100 OIG .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
| |
| I Ila Jib 100 100 100 100 100 I00 100 10o 100 100 100 100.
| |
| 0 0
| |
| 0 0 .
| |
| 0 0
| |
| 0 0
| |
| 100 100 100
| |
| -100 0
| |
| 0 0
| |
| 0 1/2 1 1
| |
| 1 1
| |
| 100.0 200.0 150.0 150.0 50.0 1563.0 1563.0 1563.0 1563 50 50 50 I
| |
| U 100 100 100 0 0 100 0 1 150.0 50.0 50 m
| |
| I 38 . Hydrostatic Test(-) 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 . 1 1iO 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, Scramsand All Other 3 (-) UIb 11 246 100 246 100 246
| |
| .100 900 900 00 246 100 00 11 150.0 150.0 940.0 50.0 1010 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) IVbV 392 392 392, 392 392 392 900 900 00 392 392 . 33 1/2 1/2 137.7
| |
| ,137.7 940.0 940.0 1010.
| |
| 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 1 125 .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 For notes, see next page.
| |
| I I
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| File No.: VY- 16Q-31 1 Page 8 of 17 1 Revision: 0 F0306-0IRO I
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| 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°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 Page 9 of 17 Revision: 0 F0306-O1RO
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| *Structural integrityAssociates, inc.
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| 4o20/20oo9:00:42 AM " o -0
| |
| '' 20 20 33 40
| |
| '0 50 8 HU1A
| |
| '
| |
| * V *' '--*,"*VO--
| |
| * ,2 17Q.
| |
| * 125
| |
| .
| |
| 14, 42 qf I [. S I0
| |
| .. .4,, , ReO.V Nod 5T 2,.
| |
| NO< 1Qto 31.7)
| |
| -S
| |
| .1Q) 1'42V
| |
| (,es' 5
| |
| : 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
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| I i
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| I I
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| I StructuralIntegrityAssociates, Inc.
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| *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 Page 11 of 17 Revision: 0 F0306-OI RO
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| StructuralIntegrityAssociates, Inc.
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| I 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) "
| |
| I Coefficient Mean Design Young's of Linear Thermal Coefficient of Thermal Thermal Thermal Yield Stress Stress Intensity I
| |
| Temperature Modulus Expansion Expansion(1) Conductivity(') Diffusivity(1) Sy Smn
| |
| ("F) 50 (xl 06 psi) 29.6 (in/100 ft) 0(2)
| |
| (10-6/in/in/F) (btu/hr/ft/°F) 2 (ft /hr)
| |
| -.
| |
| (ksi) 35.0 (ksi) 20:0 I
| |
| 70 29.5. 0 6.4 27.5 0.529 35.0 20.0 100 150 29.3 0.2 27.6 27.6 0.512 0.496
| |
| . 35.0 20.0 I
| |
| 200 28.8 1.0 27.6 0.486 32.1 20.0 250 300 350 28.3 1.9 27.4 27.2 0.467 0.453 31.0 20.0 I 27.0 0.440 400 450 500 27.7 27.3 2.8 3.7 26.7 26.3 25.9 0.428 0.413
| |
| .398 29.9 28.5 20.0 18.9 I
| |
| 550 25.5 0U387 Notes:
| |
| 600 26.7 4.7 25.0 0.374 26.8 17.3 I I. These properties are used for the transient analysis only.
| |
| : 2. Assumed equivalent to the value at 707F.
| |
| The materialpropertiesapplied 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'codeedition than that used for the originaldesign code is I
| |
| acceptablesince latereditions typically reflect more accuratematerialproperties than was publishedin prior Code editions. I I
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| I I
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| I I
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| FileNo.: VY-16Q-311 Page 12 of 17 I
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| Revision: 0 F0306-01RO I
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| I .jStructural Integrity Associates, Inc.
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| 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 Pipin Nom. . 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 Page 13 of 17 Revision: 0*
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| F0306-O1RO
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| StructuralIntegrityAssociates, Inc.
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| 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 a* 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 25 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.
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| -File No.: VY-16Q-311 Page 14 of 17 Revision: 0 F0306-0RO I
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| I StructuralIntegrityAssociates, Inc.
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| Table 4: Thermal Cycle Load Cases All other.
| |
| Region UI Load Transients Region I Region Ila Region Ilb Region U Region I. Region IV Region WVaRegion IVb Region V Vessel Regions Pressure Pressure Set Represented Temp. (IF) Temp. (IF) Temp. (IF) Temp. (IF) Temp. (IF) Temp. (IF) Temp. (IF) Temp. (IF) Temp. (oF) Temp. (IF) (psig) (psig) 1 1 100 100 100 100 .100 100 100 100 100 100. 50 1100 2 .2,24.36.38 100 100 100 100 100 100 100 100 100 100 50 50 3 3,21,34,43 150 150 125 100 150 150 283 416 I 549 . 549 1 50 1010 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 50 1010 6 7 310 310 205 100. 310 310 310 310. 310 549 50 1010 7_ 9 280 280 190 100 280 280 280 280 280 549. 50, 1010 I 8 11, 13, 15 265" 265 182.5 100 265 265 265 265 265 549 50 .1010 9 12 90 90 95 100 90 90 90 90 90 549 1010 50
| |
| *1010 10 20 265 265 182.5 100 265 265 360 454 549 549 50 11 22 150 150 125 100 150 150 225 300 375 375 50. 170 12 23 150 150 125 100 150 150 210 270 330 . 330 50 88 I 13 14 15 16 25 26 27 28 392 50 150 150
| |
| .
| |
| 392 50 150 150 246 50 125 125 100 50 100 100 392 50 150 150 392 50 150 150 450 50 247 288 507 50 343 427 565 50 440 565 565 565 565 565, 1135 so 50.
| |
| 1190 1135 1135 1135 17 30 150 .150 125 100 i 150 150 247 343 440 555 50 1060 is .31 150 150 125 100 150 150 283 416 549 565 50 1135 19 32 50 50 50 50 50 50 50 " 50 .50 502 5 675 20 33 150I ISO 125 100 150 150 200 250 300 502 50 675 21 35 275 275 187.5 100 275 275 275 275 275 549 50 885 22 37 100 100 100 1000 00 100 100 100" 100 100 50 1563 23 39 392 392 246 100 392 392 392 392 392 600 50 1375 24 40 392 392 246 100 392 392 392 392 392 539 50 940 25 41 392 392 246 100 392 392 392 392 392 549 50 1010 26 17 275 275 .. 187.5 100 275 275 275 275 . 275 539 50 1010 27 19 265 265 182.5 100 265 265 323 382 440 549 50 1010 28 4 100 100 100 100 100 100 100 100 100 549 50 1010 29 18 100 100 100 100 100 100 100 100 100 539 50. 1010 30 42 .125 125 112.5 100 125 125 180 235 290 549 50 1010 31 29. 50 50 50 50 50 50 50 50 50 532 885 885 File No.: VY-16Q-311 Page 15 of 17 Revision: 0 F0306-OIRO
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| | |
| I StructuralIntegrity Associates, Inc.
| |
| I 5.0 RESULTS OF ANALYSIS I
| |
| 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 I
| |
| 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 I
| |
| 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 I
| |
| 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 I
| |
| 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.
| |
| I Appendix B contains the fatigue usage summary for node 155.
| |
| U I
| |
| I I
| |
| I I!
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| I I
| |
| I I
| |
| FileNo.: VY-16Q-311 Page 16 of 17 Revision: 0.
| |
| I F0306-O1 RO
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| | |
| 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
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| | |
| StructuralIntegrityAssociates, Inc.
| |
| I I
| |
| I I
| |
| APPENDIX A PIPESTRESS INPUT FILE ("FWHPCi.FRE")
| |
| (Pages A1 - A38).
| |
| File No.: VY-16Q-311 Page Al of A38 Revision: 0 F0306-OIRO
| |
| | |
| I StructuralIntegrity Associates, Inc.
| |
| IDEN JB=2 *Job number (1 to 99 99)
| |
| CD=I *1=ASME Section III vA=0 *0=Calculate 2=Verify GR=-Y *Direction of gravit y
| |
| .IU=1 *Input units O=SIU 1=USA OU=I *Output units O=SIU I=USA CH=$ *Delimiter character AB=T *FREE errors =abort PL=-$Vermont Yankee$
| |
| EN=$KRE$
| |
| TI.TL BL=3 *Modelinq option:
| |
| * 3.=uniform mass for static analysis
| |
| * lumped mass for dynamic analysis
| |
| * rotational inertia ignored GL=" *Report forces/moment 0=Global 1=jocal 2=G et L SU=l *Support summary. 0=No 1=Yes 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=$SEISMIC$
| |
| THERMAL CYCLE LOAD CASES****
| |
| LCAS RF=0 CA=1 TY=0 TI.=$LC-l$ *TC-1 RF=0 CA=2 TYý0 TI=$LC-2$ *TC-2,24,36,38 LCAS
| |
| *TC-3,21,34,43 LCAS RF=0 CA=3 TYý=0 TI=$,LC-3$
| |
| *TC-5 LCAS RF=0 CA=4 TYý=0 TI=$LC-4$
| |
| , *TC-6, 8,10,14,16 LCAS RF=0 CA=5 TYý0 TI=~$LC-5$
| |
| *TC-7 LCAS RF= 0 CA=6 TY=0 .iTI=$LC-6$
| |
| RF=0 CA=7 TY=ý0 TI=~$LC-7$ *TC-9 LCAS c RF=0 CA=8 TYý0 TI=$LC-8S. *TC-11,13,15 LCAS
| |
| *TC-12 LCAS RF= 0 CA=9 TY=ý0 TIr=$LC-9$
| |
| TI=$LC-10$ *TC-20 LCAS. RF=0 CA=f0 TY=z0 *TC-22 LCAS RF=O, CA=11 TIý$LC-11$
| |
| TY=0 *TC-23 LCAS RF=0 TI=$LC-.12$
| |
| TY=0 *TC-25 LCAS RF= 0 CA=13 CA=I34 TY~=0 TI=~$LC-13$ *TC-26, 29 LCAS RF=0 CA=f4 TI=$LC-14$
| |
| TY=0 *TC-27 LCAS RF=0 .CA=15 TI=$LC-15$
| |
| TY=0 *TC-28 LCAS RF=O0 CA=16 TI=~$LC-16$
| |
| TY=0 *TC-30 LCAS RFý0 CA=I7 TI=~$LC-17$
| |
| TY=0 *TC-31 LCAS RF=0 CA=18 TI=$LC-18$
| |
| TY=0 *TC-32 LCAS RF-=0 CA=19 TI=$LC-19$
| |
| TY~=0 *TC-33 LCAS RF=O0 CA=2 0 TIL=$LC-20$
| |
| TY=0 *TC-35 LCAS RF=0 CA=21 TI=$LC-21$
| |
| TY'=0 *TC-37 LCAS RF=0 CA=22 TI=$ LC-22$
| |
| LCAS CA=2 3 TY=0 TI=$LC-23$ *TC-39 RF=0 *TC-40 LCAS CA=2 4 TY=0 TI=.$LC-24$
| |
| RF=0 *TC-41 LCAS CA=25 TY=0 TI$ LC -25$
| |
| RF=0 *TC-17 LCAS CA=2 6 TY~=0 TI=ý$LC-26$
| |
| RF=0 *TC-19 LCAS CA=27 TI=~$LC-27$
| |
| RF~=0 TY=0 *TC-4 LCAS CA=28 TI=ý$LC-28$
| |
| RF=0 TY-.0 LCAS CA=29 TI='$LC-29$ *TC-18 RF'= 0 TY=O0 *TC-42 LCAS CA=30 TI=~$LC730$
| |
| File No.: VY-16Q-311 Page A2 of A38 Revision: 0 F0306-0I RO
| |
| | |
| I VStructuralIntegrityAssociates, Inc.
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| LCAS RF=0 CA=31 TY=0 TI=$LC-31 *TC-29 I
| |
| LCAS RF=6.CA=32.TY=6 TI==$SAM$
| |
| **
| |
| ********
| |
| WEIGHT CASES****
| |
| **** **** *.***
| |
| I LCAS CA=101 LCAS CA=102 RF=1 RF=2 TY=3 TY=4 TI=$OPERATING WEIGHT$
| |
| TI=$HYDROTEST WEIGHT$ I TCAS CA=201 THERMAL TRANSIENT CASES****
| |
| RP=I 1TI=$Design Hydrotest +$
| |
| I
| |
| *TCAS CA=202 TCAS CA=203 TCAS CA=2 04 RP=I 1TI=$Design Hydrotest -$
| |
| RP=I 1TI=$Startup +$
| |
| RP=I - TI=$TRoll & Inc. PWR1 -$
| |
| I TCAS CA=2 05 RP=I TI=$TRoll & Inc. PWR2 +$
| |
| TCAS CA=206 TCAS CA=207 TCAS CA=208 RP=I TI=$TRoII & Inc. PWR3 +$
| |
| RP=I
| |
| * TI=$DlyReduction to 75% -5 RP=I TI=$DlyReduction to 75%
| |
| +$
| |
| I I
| |
| TCAS CA=209 RP=1
| |
| * TI=$WklyReduct to 50% -$
| |
| TCAS CA=210 RP=1
| |
| * TI=$WklyReduct to 50% +$
| |
| TCAS CA=211 RP=1
| |
| * TI=$LOFWH+TT .1 $
| |
| TCAS CA=212 RP=1 TI=$LOFWH+TT 2 -$
| |
| TCAS CA=213 TCAS CA=214 TCAS CA=215 RP=1 TI=$LQFWH+TT 3 +$
| |
| RP=I TI=$LOFWH+TT 4 +$
| |
| RP=1 TI=$LOFWH+PFWHTR Byp -$
| |
| I TCAS CA=216 RP=1 TI=$LOFWH+PFWHTR Byp +$
| |
| TCAS CA=217
| |
| .TCAS CA=218 RP=1 TI=$SCRAM+TT+AllOtrScm -:
| |
| RP=1 TI=$SCRAM+TT+AIlOtrScm -!
| |
| I TCAS CA=219 RP=1 TI=$HotStandby 1 +$
| |
| TCAS CA=2 20 TCAS CA=221 TCAS CA=222 RP=1 TI=$HotStandby 2 +$
| |
| RP=1 TI=$HotStandby 3 -$
| |
| RP=1 TI=$Shutdown 1 -$
| |
| I TCAS CA=2 23 RP=1 TI=$Shutdown 2 -$
| |
| TCAS CA=224 TCAS CA=225 TCAS CA=226 RP=1 TI=$Shutdown 3 -$
| |
| RP=1 TI=$SCRAM+LOFWPI +$
| |
| RP=1 TI=$SCRAM+LOFWP2 -$
| |
| I TCAS CA=227 TCAS CA=228 TCAS CA=229 RP=1 TI=$SCRAM+LOFWP3 +$
| |
| RP=1 TI=$SCRAM+LOFWP4 +$
| |
| RP=1 TI=$SCRAM+LOFWP5 -$
| |
| U TCAS .CA=230 RP= 1 Ti=$SCRAM+LOFWP6 +$
| |
| TCAS CA=231 TCAS CA=232 TCAS CA=233 RP=1 TI=$SCRAM+LOFWP7 +$
| |
| RP=1 TI=$SCRAM+LOFWP8 -s RP=1 TI=$SCRAM+LOFWP9 +$
| |
| I TCAS CA=234 RP=1 TI=$SCRAM+LOFWP10+$
| |
| TCAS CA=235 TCAS CA:236 RP=1 TI=$SCRAM+SRVBLDN1-$
| |
| RP=1 TI:$SCRAM+SRVBLDN2-$
| |
| I TCAS CA=237 RP=1 TI=$Hydro Test +$
| |
| TCAS CA=2 3.8 TCAS CA=239 TCAS CA=240 RP=1 TI=$Hydro Test -$
| |
| RP=1 TI=$SCRAM+TG+OPresl -$
| |
| RP=I TI=$SCRAM+TG+OPres2 -$
| |
| I TCAS CA=241 RP=I TI=$SCRAM+TG+OPres3 -$
| |
| TCAS CA=2422 TCAS CA=243 RP=I TI=$HotSbyFWcyc +$
| |
| RP=I I TI=$HotSbyFWcyc +$ I
| |
| ***SEISMIC File No.: VY-16Q-311 CASES****
| |
| Page A3 of A38 I Revision: 0 F0306-O IRO I
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| | |
| I ~Structural IntegrityAssociates, 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 C1=103 CY=10 TI=~$OBE$
| |
| CCAS RF=i CA=401 SS=I ME=I EQ=3 C1=102 C2=103 TIý$EQUATION 9 LEVEL B$
| |
| CCAS RF=I CA=402 SS=I ME=3 Fl=I C1=.103 C2=6 C3=32 TI=$NORMAL+/-OBE$
| |
| CCAS RF=1 CA=403 SS=I ME=3 F1=-l C1=~103 C2=~6 C3ý32 TI=$NORMAL-OBE$
| |
| LOAD SETS****
| |
| *RF field is the highest temperature and pressure of the transient
| |
| *PR and MO fields are the final temperature and pressure of the transient LSE] RF= 1 RP=I CY=120 PR=1 MO=1 TR=+201 TI=$Design Hydrotest + LS -1$
| |
| LSET RF=ý2 RP=I CY=120 PR=2 MO=2 TR=-202 TI=$Design Hydrotest - LS -2$
| |
| LSET RFý3 RP=4 CY=300 PR=3 MO=3, TR=+203 TI=$Startup + LS -3$
| |
| LSET RF=3 RP=I CY=610 PR=28 MO=28 TR=-204 TI=$TRoll & Inc. PWRI - LS -4$
| |
| LSET RFý4 RP=1 CY=599 PR=4 MOý4 TR=+205 TI=$TRoll & Inc. PWR2 + LS- -5$
| |
| LSET RFý5 RP=I CY=599 PR=5 MO=5 TR=+206 TI=$TRoll & Inc. PWR3 + LS- -6$
| |
| LSET RFý5 RP=I CY=10000 PR=6 .MO=6 TR=-207 TI=$DlyReduction to 75% - LS- -7$
| |
| LSET RP=I CY=I0000 PR=5 MO=5 TR=+208 TI=$DlyReduction to 75% + LS- -8$
| |
| RFý5 LSET RP~= CY=2000 PR=7 MO=7 TR=-209 TI=$WklyReduct to 50% - LS- -9$
| |
| RF=5 LSET RP=I CY=-2000 PR=5 MO=5 TR=+210 TI=$WklyReduct to 50% + LS- -10$
| |
| RF=ý5 LSET RP=I CY=310 PR=8 MO=8 TR=-211 TI=$LOFWH+TT I - LS- -11$
| |
| RF=ý8 LSET RP~= CY=10 PR=9 MO=9 TR=-212 TI=$LOFWH+TT 2.- LS- -12$
| |
| LSET RF'ý8 RP=1 CY=10 PR=8 MO-=8 TR-=+213 TI=$LOFWH+TT 3 + LS- -13$
| |
| LSET RF==5 RP=I CY=10 PR=5 MO=5 TR=+214 TI=$LOFWH+TT 4 + LS--14$
| |
| LSET RF'=5 RP=1 CY=70 PR=8 MO=8 TR=-215 TI=$LOFWH+PFWHTR Byp - LS- -15$
| |
| LSET .RF==5 RP~= CY=70 PR=5 MO=5 TR=+216 TI=$LOFWH+PFWHTR Byp + LS- -16.$
| |
| LSET RP=5, RP=I CY=289 PR=26 MO=26 TR=-217 TI=$SCRAM+TT+AIIOtrScm - LS- -17$
| |
| LSET RF==2 6 RP=I CY=289 PR=29 MO=29 TR=-218 TI=$SCRAM+TT+AllOtrScm - LS- -18$
| |
| LSET *RF'=27 RP=1 CY~=300 PRý2 7 MO~=2 7 TR=+219 TI=$HotStandby 1 + LS-19$
| |
| LSET RF=10 RP~ 1 CY~=300 PRý 10 MO~=10 TR=+220 TI=$HotStandby 2 + LS-20$
| |
| LSET RF==10 RP~=l CY=~300 PR=3 MO=3 TR=- 221 TI=$HotStandby 3 - LS-21$
| |
| LSET RF==3 RP=1 CY~=300 PR=11 MO~=11. TR=-222 TI=$Shutdown 1 - LS-22$
| |
| LSET RF~ll RP= 1 CY=300 PR~=12 MO= 12 TR=-223 TI=$Shutdown 2 - LS-23$
| |
| LSET RF=-12 Rp~=1 CY=300 PR~=2 MO~=2 TR=-224 TI=$Shutdown 3 - LS-24$
| |
| LSET RFý1l3 RP=1 CY~=10 PR=13 M0~=1 3 TR=+225 TI=$SCRAM+LOFWPI + LS-25$
| |
| LSET RF=13 RP~=1 CY~=10 PR=14 MO=1 4 TR=-226 TI:$SCRAM+LOFWP2 - LS-26$
| |
| LSET RF~=15 RP~l CY=10 PR=1,5 MO~=15 TR=+227 TI=$SCRAM+LOFWP3 + LS-27$
| |
| LSET RF=16 RP~l CY=10 PR=16 MO~l 6 TR=+228 TI=$SCRAM+LOFWP4 + LS-28$
| |
| LSET RF=16 RIP-- CY=10 PR=31 MO~=31 TR=-229 TI:$SCRAM+LOFWP5 - LS-29$
| |
| LSET RE'=17 Rh= 1 CY=10 PR~=17 MO=17 TR=.+230 TI=$SCRAM+LOFWP6 + LS-30$
| |
| LSET RF=18. RP=1 CY=10 PR='18 MO=18 TR=+231 TI=$SCRAM+LOFWP7 + LS-31$
| |
| LSET RFý 18 RP=1 CY=10 PR~=19 MO~=19 TR:-232 TI=$SCRAM+LOFWP8 - LS-32$
| |
| LSET RF=20 RP~=1 CY=1O PR=2 0 MO=2 0 TR=+233 TI=$SCRAM+LOFWP9 + LS-33$
| |
| LSET RF~=3 RP~ 1 CY=10 PRr=3 MO=3, TR=+234 TI=$SCRAM+LOFWP10+ LS-34$
| |
| LSET PFý5 RP~=1 CY~1 PR~=2 1 MOý21 TR=-235 TI=$SCRAM+SRVBLDN1,- LS-35$
| |
| LSET RE'=21 RP~=1 CY= 1 PR=2 MO=2 TR=-236 TI=$SCRAM+SRVBLDN2.- LS-36$
| |
| LSET *RF=22 RP+1 CY=1 PR=~22 MO=22 TR=+237 TI=$Hydro Test + LS-37$
| |
| LSET RF~=2 RP= 1 CY- 1 PR~=2 MO=~2 TR=-238 TI=$Hydro Test - LS-38$
| |
| LSET RF=23 RP=1 CY=289 PR=23 MO=~23 TR=-239 TI:$SCRAM+TG+OPresl - LS-39$
| |
| LSET RF=24 RP= 1 CY=289 PR=24 MO=~24 TR=-240 TI=$SCRAM+TG+OPres2 - LS-40$
| |
| File No.: VY-16Q-31I Page A4 of A38 Revision: 0 F03 06-01 RO
| |
| | |
| I VStructural IntegrityAssociates, Inc.
| |
| LSET RFý25 RP=I CY=289 PR=25 MO=25 TR=-241 TI=$SCRAM+TG+OPres3 - LS-41$
| |
| I LSET RF=30 RP=1 CY=300 PR=30 MO=30 TR=+242 TI=$HotSbyFWcyc + LS-42$
| |
| LSET RF=3 RP=1 CY=300 PR=3 MO=3 TR=+243 TI=$HotSbyFWcyc + LS-43$
| |
| LSET RFý6 CY=5 FL-=1 PR=6 MO=402 TI=$NORMAL+OBE LS-132$
| |
| LSET RFr6 CY=5 FL=I PR=6 MO=403 TI=$NORMAL-OBE LS-133$
| |
| ***********
| |
| RESPONSE SPECTRA****
| |
| **************
| |
| *SSE response spectra conservatively used I
| |
| SPEC FS=OBE EV=I ME=3 FP=I TI=$RESPONSE$
| |
| LV=I DX=I DY=I DZ=I DI=X I
| |
| 0.30/0.125 0.80/0.300 2.00/0.6[50 3.00/0.725 3.50/1.000 4.40/1.200 5.00/1.900 5.75/2.850 6.00/3.3-75 14.00/1.325 19.00/1.600 21.00/1.0(00 22.00/0.800 8-.25/3.375 9.00/3.000 10.00/2.400 30.00/0.700 36.00/0.650 I
| |
| DI=Y 0.30/0.075 4.40/0.500 1.25/0.2 50 4.80/0.6 00 1.75/0.325 2.40/0.450 7.25/0.600 12.00/1.450 16.00/1.9 00 18.00/1.700 20.00/0.750 7.50/0.700 2.75/0.475 3.80/0.500 8.50/0.700 10.00/0.925 25.00/0.4.50 30.00/0.350 I
| |
| 36.00/0.325 36.10/0.3 25 36.20/0.325 .36.30/0.325 36.40/0.325 36.50/0.325 DI=Z 0.30/0.150 1.00/0.3 50 2.00/0.625 4.00/1.000 4.50/1.400 5.00/2.000 I
| |
| 5.75/2.950 6.00/3.4 5o :6.25/3.800 8.75/3.800 10.00/2.625 12.0/2.150 15.00/1.300 17.50/1.4 50 20.00/0.875 30.00/0.650 36.00/0.650 36.10/0.650
| |
| ***
| |
| *******
| |
| MATERIAL
| |
| ** *** **
| |
| PROPERTIES
| |
| *********
| |
| **
| |
| * *****
| |
| I
| |
| * 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 I
| |
| MATO MATO MATO TE=50 TE=70 TE=100 EH=29. 6 EX=0 SM=20 SY=35 EH=2 9.5 EX=0 SM=20 EH=29. 3 EX=0. 2 SM=20. 0 SY=35 SY=35 I MATO TE=2 00 EH=28.8 EX=I. 0 SM=20..0 SY=32. 1 MATD MATO MATD TE=300 TE=400 TE=500 EH=28 .3 EX=1. 9 SM=20. 0 SY=31 EH=27 .7 EX=2. 8 SM=20.O0 SY=29. 9 EH=2 7.3 EX=3. 7 SM=18. 9 SY=28.5 I
| |
| TE=600 EH=26. 7 EX=4 . 7 SM=17. 3 SY=26. 8 I
| |
| MATD
| |
| *** 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 SO= ST=1
| |
| *FEEDWATER Valves - V2-27A, V2-28A, V2-29A WT=l.218 MA=204.28 IN=0 I 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 Page A5 of A38 Revision: 0 F0306-OIRO
| |
| | |
| I ¶ StructuralIntegrity 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 TEý100'PR=1010 OPER CA=29 TE=100 PR=1010
| |
| *Same for all regions OPER CA=2 TE=100 PR=50 OPER CA=19 TE=50 PR=675 OPER CA=31 TE=50 PR==885
| |
| *Unique OPER CA=3 TE=I50 PR=1010 OPER. CA=4 TE=260 PR=1010 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=10 TE=265 PR=1010 OPER CA=II TE=150 PR=170 OPER CA=12 TE=150 PR=8 8 OPER CA=13 TE=392 PR=1190 OPER CA=14 TE=50 PR=1135 OPER CA=15 TE=150 PR=1135 OPER CA=16 TE=50 PR=1135 OPER CA=17 TE=150 PR=1060 OPER CA=18 TE=150 PR=1135 OPER CA=2.0 TE=150 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=265 PR=1010 File No.: VY-16Q-311 Page A6 of A38 Revision: 0 F0306-0I RO
| |
| | |
| I Structural Integrity Associates, Inc.
| |
| OPER CA=30 .TE-125 PR=1010 I
| |
| TRAN TRAN CA=20 CA=20 IS=1 FS=1 I S= 1 FS=1 IT=70 FT=100 TT=1800 FL=200 IP=15 FP=1115 TP=1800 IT=100 FT=1.0 TT=0 FL=200 IP=1115 FP=65 TP=0 I
| |
| TRAN CA=20 I
| |
| TRAN CA=20 IS=1 FS=1 IT=100 FT=15( TT=16164 FL=200 IP=65 FP=1025 TP=16164 TRAN CA=20 I S= 1 FS=1 IT=150 FT=10( TT=0 FL=1377 IP=1025 FP=1025 TP=0 TRAN CA=20 IS=1 FS=1 IT=100 FT=26( TT=0 FL=1377 IP=1025 FP=1025 TP=0 TRAN CA=20' IS=1 FS=1 IT=260 FT=392 TT=1800 FL=9180 IP=1025 FP=1025 TP=1800 TRAN TRAN TRAN CA=20 CA=20 CA=20I IS=1 FS=1 IS=1 FS=1 I S=1 FS -I IT=392 FT=310 TT=900 FL=6885 IP=1025.FP=1025 TP=900 IT=310 FT=392 TT=900 FL=6885 *IP=1025 FP=1025 TP=900 IT=392 FT=280 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 I
| |
| IS= 1 FS=1 IT=280 FT=392 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 TRAN TRAN TRAN CA=21L CA=21:
| |
| CA=21i IS-=1 FS=1 IS=1 FS=1 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 I
| |
| TRAN CA=21, IS=1 FS=1 IT=90 FT=265 TT=900 FL=1377 IP=1025 FP=1025 TP=900 TRAN TRAN TRAN CA=21i CA=21(
| |
| CA=21I IS=1 FS=1 IS=1 FS=I IS=1 FS=1 IT=265 FT=392 TT=1800 FL=4590. IP=1025 FP=1025 TP=1800 IT=392 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 I
| |
| IS=1 FS=1 IT=392 FT=275 TT=60 FL=10098 IP=1025 FP=1025 TP=60 TRAN TRAN TRAN CA=21 CA=21ý CA=22(
| |
| IS=1 FS=I
| |
| *IS=I FS=1
| |
| *IS=I FS=1 IT=275 FT=100 TT=900 FL=275.4 IP=1025 *FP=1025 TP=900 IT=265 FT=265 TT=0 FL=200 IP=1025 FP=1025 TP=0 IT=265ý.FT=265 TT=0 FL=200 IP=1025 FP=1025 TP=0 I
| |
| TRAN CA=22(
| |
| TRAN CA=22M IS=1 TRAN CA=227 I S= 1 TRAN CA=224 IS=1 FS=1 IT=265 FT=150 TT=4140 FL=200 IP=1025 FP=1025 TP=4140 FS=I IT=150 FT=150 TT=0 FL=200 IP=1025 FP=185 TP=0 FS=1 IT=150 FT=150 TT=0 FL=200 IP=185 FP=103 TP=0 I
| |
| FS=I IT=150 FT=100 TT=8280 FL=200 IP=103 FP=65 TP=8280 TRAN CA=22E Is=1 TRAN CA=22E Is=1 TRAN CA=227 IS=1 FS'= 1 FS=1 IT=392 FT=392 TT=12 FL=200 IP=1025 FP=1.205 TP=12 FS=1 IT=392 FT=50 TT=0 FL=3672 IP=1205 FP=1150 TP=0' 1 TRAN CA=228 Is=1 FS=I IT=50 FT=150 TT=1380 FL=200 IP=1150 FP=1150 TP=1380 TRAN CA=229 IS=E1 TRAN CA=230 IS=1 TRAN CA=231 Is=1 FS=I IT=150 FT=150 TT=0 FL=200 IP=1150 FP=1150 TP=0 FS=I IT=150 FT=50 TT=0 FL=2754 IP=1150 FP=900 TP=0 FS=I IT=50 FT=150 TT=3060 FL=200 IP=900 FP=1075 TP=3060 I
| |
| TRAN CA=232 IS=1 FS=I IT=150 FT=I50 TT=0 FL=200 IP=1075 FP=1150 TP=0 TRAN CA=233 I S=1 TRAN CA=234 Is=1 TRAN CA=235 I S=1 FS:I IT=150 FT=50 TT=0 FL=1560.6 IP=1150 FP=690 TP=0 FS:I IT=50 FT=150 TT=300 FL=200 IP=690 FP=690. TP=3M0
| |
| .FS=I IT=150 FT=150 TT=8964 FL=200 IP=255 FP=1025 TP=8964 I
| |
| TRAN CA=236 ISr=1 F S=1 IT=392 FT=275 TT=60 FL=10098 IP=1025 FP=900 TP=60 TRAN CA=237 I S= 1 TRAN CA=238 IS=1
| |
| -FS=I IT=275 FT=100 TT=900 FL=275.4 IP=900 FP=65.TP=900
| |
| .FS=I IT=100 FT=100 TT=0 FL=200IP=65 FP=1578 TP=0 I
| |
| TRAN CA=239 I*S= 1 FS=I IT=100 FT=100 TT=O FL=200 IP=1578 FP=65 TP=0 TRAN CA=240 Is=1 TRAN CA=241 Is=1 Is=1 FS=1 IT=392 FT=392 TT=60.FL=10098. IP=1025 FP=1390 TP=60 FS=I" FS=I FS=I IT=392 FT=392 TT=900 FL=275.4 IP=1390 FP=955 TP=900 FS=1 IT=392 FT=392 TT=900 FL=275.4 IP=955 FP=1025 TP=900 I
| |
| TRAN CA=242 I S= 1 IT=100 FT=125 TT=60 FL=200 IP=1025 FP=1025 TP=60 TRAN CA=243 Is.=1 PAIR CA=201 CO=27. 6 IT=125 FT=150 TT=210 FL=200 IP=1025 FP=1025 TP=210 DI=0.521 EX=6. 4
| |
| * Tavg=85 I
| |
| EX=6. 4
| |
| * Tavg=100 PAIR.
| |
| PAIR PAIR CA=202 CA=203 CA=204 CO=27 .6 CO=27. 6 CO=27. 6 DI=0. 512 DI=0. 504 DI=0. 504.
| |
| EX=6. 4
| |
| * Tavg=125 EX=6. 4
| |
| * Tavg=125 I
| |
| PAIR CA=205 CO=27. 6 DI=0. 490 EX=6. 4 " Tavg=180 PAIR PAIR PAIR CA=206.
| |
| CA*-207 CA=208 CO=2 7.1 CO=27.0 CO=27.0 DI=0.446 DI=0.440 DI=0. 440 EX=6.4 EX=6. 4 EX=6. 4
| |
| * Tavg=326
| |
| *
| |
| "
| |
| Tavg=351 Tavg=351 I
| |
| EX=6. 4
| |
| * Tavg=336 CO=27. 1 I
| |
| PAIR CA=-209 DI=0.444 File No.: VY-16Q-311 Page A7 of A38 Revision: 0 F0306-0IRO I
| |
| | |
| StructuralIntegrityAssociates, Inc.
| |
| 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 PAIR CA=213 CO=27. 6 DI=0. 490 EX=6. 4 Tavg=178 PAIR CA=214 CO=27. 1 DI=0. 445 EX=6. 4 Tavg=329 PAIR CA=215 CO=27 .1 DI=0. 445 EX=6.4 Tavg=329 PAIR CA=216 CO=27. 1 DI=0 .445 EX=6.4 Tavg=329 PAIR CA=2 17 CO=27 .1 DI=0.444 EX=6. 4 Tavg=334 PAIR CA=218 CO=27.6 DI=0. 488 EX=6.4 Tavg=188 PAIR CA=219 CO=27 .3 DI=0. 463 EX=6. 4 Tavg=265 PAIR CA=220 CO=2 7.3 DI=0.463 EX=6. 4 Tavg=265 PAIR CA=221 CO=27.. 6 DI=0.4 83 EX=6. 4 Tavg=208 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=27.16 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=0. 496 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=2 34 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=2 36 CO=27. 6 DI=0. 488 EX=6. 4 Tavg=188 PAIR CA= 237 CO=2 7. 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=2 39 CO=26 7 DI=0.430 EX=6. 4 Tavg=392 PAIR CA=240 CO=2 6.7 DI=0.430 EX=6. 4 Tavg=392 PAIR CA=224 1 CO=26.7 DI=0. 430 EX=6. 4 Tavg=392 PAIR CA=2 42 CO=27. 6 DI=O. 508 EX=6. 4 Tavg=113 PAIR CA=2 43 CO=27. 6 DI=0 .500 EX=6. 4 Tavg=138
| |
| *REGION I GEOMETRY
| |
| * RUN 1 FROM ANCHOR. HD36 TO HPCI brnCH- FDW-16 LINE A MATL CD=106 CROS CD=1 COOR PT=5 AX=0 AY=0 AZ=0 *ANCHOR HD36 JUNC PT=5 TANG PT=9 DZ=-2.75 EW=1l TANG 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 CA=201 IS=1 FS=1 IT=70 FT=100 TT=1800 FL=200 IP=15 FP=1115 TP=1800 TRAN CA=202 IS=1 FS=1 IT=100 FT=100 TT=0 FL=200 IP=1115 FP=65 TP=0 TRAN CA=203 IS=1 FS=1 IT=100 FT=150 TT=16164 FL=200 IP=65 FP=1025 TP=16164 TRAN CA=204 IS=1 FS=I IT=150 FT=100 TT=0 FL=1377 IP=1025 FP=1025 TP=0 TRAN CA=205 IS=l FS=1 IT=100 FT=260 TT=0 FL=1377 IP=1025 FP=1025 TP=0 T RAN CA=206 IS=1 FS=1 IT=260 FT=392 TT=1800 FL=9180 IP=1025 FP=1025 TP=1800 FileNo.: VY-16Q-311 Page A8 of A38 Revision: 0 F0306-OIRO
| |
| | |
| Structurallntegrifty AssoCiates, Inc.
| |
| I TRAN CA=207 I3=1 FS=1 IT=392 FT=310 TT=900 FL=6885 .IP=1025 FP=1025 TP=900 TRAN CA=208 I3=1 FS=1 IT=310 FT=392 TT=900 FL=6885 IP1=025 FP=1025 TP=900 TRAN CA=209 TRAN CA=210 13=1 FS=1 IT=392 FT=280 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 I3=1 FS=1 IT=280 FT=392 TT=1800 FL=4590 IP=1025 FP=1025 TP=18Q0 FS=I IT=392 FT=265 TT=1800 FL=4590 IP=1025' FP=1025 TP=1800 I
| |
| TRAN CA=211 IS= 1 FS=1 TRAN CA=212 TRAN CA=213 TRAN CA=214 13=1 FS=1 IT=265 FT=90 TT=360 FL=1377 IP=1025 FP=1025 TP=360 I3=1 FS=1 IT=90 FT=265 TT=900 FL=1377 IP=1025 FP=1025 TP=900 I 3=1 FS=1 IT=265 FT=392 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 I
| |
| -TRAN CA=215 13=1 IT=3.92 FT=265 TT=90 FL=9180 IP=1025 FP=1025 TP=90 TRAN CA=216 TRAN CA=217 13=1 FSý=I FS=1 IT=265 FT=392 TT=180 FL=9180 IP=1025 FP=1025 TP=180' 13=1 FS=1 IT=392 FT=275 TT=60 FL=10098,IP=1025 FP=1025 TP=60 I
| |
| TRAN CA=218 13=1 IT=275 FT=100 TT=900 FL=275.4 IP=1025 FP=1025 TP=900 TRAN CA=219 TRAN CA=2 20 TRAN CA=221
| |
| *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 0 I
| |
| TRAN CA=222 IS=1 FS=1 IT=150. FT=150 TT=0 FL=200 IP=1025 FP=485 TP=0 TRAN CA=223 TRAN CA=224 TRAN CA=225 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 I
| |
| TRAN CA=226 TRAN CA=227 TRAN CA=228 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 I
| |
| TRAN CA=229 IS=1 FS=I IT=150 FT=50 TT=0 FL=2754 IP=1150FP=900 TP=0 TRAN CA=230 TRAN CA=231 T RAN CA=232 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 I
| |
| I TRAN CA=233 IS=21 FS=1 IT=50 FT=150 TT=300 FL=200 IP=690 FP=690 TP=300 TRAN .CA=234 IS=1 FS=1 IT=150 FT=150 TT=8964 FL=200 IP=255 FP=1025 TP=8964 TRAN CA=235 IS=1 FS=1 IT=392 FT=275 TT=60 FL=10098 IP=1025 FP=900 TP=60 TRAN CA=236 IS=1 FS=1 IT=275 FT=100 TT=900 FL=275.4 IP=900 FP=65 TP=900 TRAN CA=237 TRAN CA=2 38 TRAN CA=239 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 I
| |
| TRAN CA=240 IS=1 FS=1 IT=392 FT=392 TT=900 FL=275.4 IP=1390 FP=955 TP=900 TRAN CA=241 TRAN CA=242 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 I TRAN CA=243 IS=1 FS=1 IT=125 FT=150 TT=210 FL=200 IP=1025 FP=1025 TP=210 FAIR CA=201 PAIR CA=202 CO=27. 6 DI=0. 521 EX=6.4
| |
| * Tavg=85 I
| |
| CO=2 7.6 DI=0. 512 EX=6.4
| |
| * Tavg=100 PAIR PAIR PAIR CA=203 CA=204 CA=205 CO=27.6 CO=27 .6 CO=27.6 DI=0. 504 DI=0. 504 DI=0. 490 EX=6.4 EX=6.4 EX=6. 4
| |
| *
| |
| *
| |
| * Tavg=125 Tavg=.125 Tavg=180 I
| |
| PAIR CA=206 CO=27.1 DI=0. 446 I
| |
| * PAIR CA=207 EX=6. 4 Tavg=326 PAIR CA=208 CO=27 .0 DI=0 440 EX=6. 4
| |
| * Tavg=351 PAIR CA=209 CO=27 .0 DI=0. 440 EX=6.4 7*
| |
| Tavg=351 CO=27.1 DI=0. 444 EX=6.4 Tavg=336 I
| |
| PAIR CA=210 PAIR CA=211 CO=27. 1 DI=0 444 EX=6. 4
| |
| * Tavg=336 PAIR CA=212 CO=27 .1 DI0 .445 EX=6. 4
| |
| * Tavg=329 CO=27. 6 DI=0. 490 EX=6 .4
| |
| * Tavg=178 PAIR CA=213 CO=27 .6 DI=0. 490 U
| |
| * PAIR CA=214 EX=6. 4 Tavg=178 PAIR CA=215 CO=27 .1 DI=0. 445 EX=6. 4
| |
| * Tavg=329 CO=27. 1 DI=0.445 EX=6.4
| |
| * Tavg=329 PAIR CA=216 CO=27.1 DI=0.445 EX=6. 4
| |
| * Tavg=329 PAIR CA=217 CO=27.1 File No.: VY- 16Q-311 DI=0. 444 EX=6. 4
| |
| * Tavg=334 Page A9 of A38 I
| |
| Revision: 0 F0306-01 RO I
| |
| | |
| 3 StructuralIntegrityAssociates, Inc.
| |
| PAIR CA=218 CO=27. 6 DI=0.488 EX=6. 4 Tavg=188 PAIR CA=219 CO=27 .3 DI=0.463 EX=6. 4 Tavg=265 PAIR CA=220 CO=27. 3 DI=0.463 EX=6.4 Tavg=265 PAIR CA=221 CO=27. 6 DI=0. 483 EX=6.4 Tavg=208 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 mI=0. 5i2 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=0. 496 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=2 6.7 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 DI00.430 EX=6.4 Tavg=392 PAIR CA=242 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
| |
| *REGION III GEOMETRY CROS CD=1
| |
| *JUNC PT=10 TANG PT=11 DZ.=-I EW=1 TANG PT=15 DZ=-4.17 TANG PT=20 DZ=-0 333 EW=1 *TA=I CROS CD=2 VALV PT=22 DZ=-1.333 PL=1 MA=2.7 *VALVE V2-27A VALV PT=25 DZ=-1.333 PL=2 EW=1 *TA=I CROS CD=1 TANG PT=30 DZ=-2, 792 LUMP PT=30 MA=1.285 TANG PT=38 DZ=-4 6 TANG PT=40 DZ=-6. 317 TANG PT=45 DZ=-0. 625 EW=1 *TA=I CROS CD=2 VALV PT=47 DZ=-1.792 PL=1 MA=2.7 *VALVE V2-28A VALV PT=50 DZ=-1.792 PL=2 EW=1 *TA=I CROS CD=1
| |
| *TANG PT=55 DZ=-2.791 EW=I TANG PT=55 DZ=-.791 EW=1
| |
| *BRAD PT=65 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 Page A1O of A38 Revision: 0 F0306-OIRO
| |
| | |
| SStructurallIntegrityAssociates, Inc.
| |
| I VALV CROS TANG PT=75 CD=3 PT=78 DY=1.333 PL=2 DY=I.25 EW=l *TA=1 U
| |
| TANG PT=80 DY=3.5 TANG CROS BRAD PT=82 CD=4 PT=85 DY=2.667 RA=2 EW=I EW=I I
| |
| CROS CD=3 TANG TANG PT=90 PT=95 DX=2.875 DX=2.875 EW=I I CROS CD=4 BRAD CROS TANG PT=100 CD=3.
| |
| PT=105 RA=2 DX=1.12 EW=I DZ=-1.12 I
| |
| TANG PT=110 DX=3.477 DZ=-3.477 EW=1 CROS TANG CD=4 PT=115 DX=0.7071 DZ=-0.7071.EW=l I
| |
| ------------------------------------------
| |
| *END REGION III
| |
| ------------------------------------------
| |
| *BEGIN REGION IV
| |
| - ----------------
| |
| I
| |
| ---------------
| |
| *OPER cards same as those for regions I and III TRAN CA=201 Is=1 FS=I IT=70 FT=100 TT=1800 FL=100 IP=15 FP=1115 TP=1800 I
| |
| TRAN CA=202 TRAN CA=203 I5=1 FS=I IT=100 FT=100 TT=0 FL=100 IP=1115 FP=65 TP=0 Is=1 FS=I1 IT=100 FT=150 TT=16164 FPL=100 IP=65 FP=1025 TP=16164 I
| |
| TRAN CA=204 Is=1 IT=150 FT=100 TT=0 FL=688.5 IP=1025 FP=1025 TP=0 1s=1 FS=I .IT=100 FT=260 TT=O FL=688.5 IP=1025 FP=1025 TP=0 TRAN CA=205 TRAN CA=206 TRAN CA=207 I5=1 FS=1 IT=260 FT=392 TT=1800 FL=4590 IP=1025 FP=1025 TP:1800 I.s=1 FS*I IT=392 FT=3 10 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 I
| |
| TRAN CA=208 15=1 FS-1 IT=310 FT=392 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 TRAN CA=209 TRAN CA=210 TRAN CA=211 Is=1 FS=I IT=392 FT=280 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 IS=d FS=I IT=280 FT=392 TT=1800 FL=2295 IP=1025 FP=1025 TP-1800 Is=1 FS=I IT=392 FT=265 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 I
| |
| TRAN CA=212 TRAN CA=213 TRAN CA=214 IS=l FSI IT=265 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 I
| |
| TRAN CA=215 IS=I FS=I IT=392 FT=265 TT=90 FL=4590 IP=1025 FP=1025 TP=90.
| |
| TRAN CA=216 TRAN CA=2 17 TRAN CA=218 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 I
| |
| TRAN CA=219 *IS= FS=1 IT=265 FT=265 TT=0 FL=100 IP=1025 FP=1025 TP=0 TRAN CA=220 *IS=1 FS=I IT=265 FT=265 TT=0 FL=100 IP=1025 FP=1025 .TP=0 TRAN CA=221 TRAN CA=222 IS=I IS=l FS=I FS=1 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 I
| |
| TRAN CA=223 TRAN CA=224 TRAN CA=225 IS=1 IS=I IS=I FS=1 FS=I FS=I 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 I
| |
| TRAN CA=226 IS=I FS=1 IT=392 FT=50 TT=0 FL=1836 IP=1205 FP=1150 TP=0 TRAN CA=227 TRAN CA=228
| |
| *IS=1 Is=i PS=I1
| |
| *IS=I 85=1 IT=50 FT=150 TT=1380 FL=i00 IP=1150 FP=1150 TP=1380 FS=I IT=150 FT=150 TT=0 FL=100 IP=1150 FP=1150 TP=0' IS:I FS=I IT=150 FT=50 TT=0 FL=1377 IP=1150 FP=900 TP=0 I
| |
| TRAN CA=229 TRAN CA=230 TRAN CA=231 IS=I FS=1 IT=50 FT=150 TT=3060 FL=100 IP=900 FP=1075 TP=3060 IS=I FS= IT=150 FT=150 TT=0 FL=100 IP=1075 FP=1150 TP=0. I File No.: VY-16Q-311 Page All of A38 Revision: 0 I
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| F0306-O1RO
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| structural Integrity Associates,,Inc. Inc.
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| AssoCiates, TRAN CA=232 IS=1 FS=-1 IT=150 FT=50 TT=0 FL=780.3 IP=I150 FP=690 TP=0 lntegrity TRAN CA=233 IS--I IT=50 FT=150 TT=300 FL=100 IP=690 FP=690 TP=300 IS=1 FS=1
| |
| ! Structural TRAN CA=234 FS=1 IT=150 FT=150 TT=8964 FL=100 IP=255 FP=1025 TP=8964 TRAN CA=23 5 IS=1 FS=1 IT=392 FT=2 7 5 TT=60 FL=5049 IP=1025 FP=900 TPý60 TP=900 TRAN CA=2 36 IS=1 FS=-1 IT=275 FT=100 TT=900 FL=137.7 IP=900 FPý65 TT=0 FL=100 IP=65 FP=1578 TP=0 TRAN CA=237 IS=1 FS=1 IT=100 FT=100 TP=0 TRAN CA=238 IS=1 FS=1 IT=100 FT=100 TT=0 FL=100 IP=1578 FP=65 FT=392 TT=60 FL=5049 IP=1025 FP=1390 TP=60 TRAN CA=239 IS=1 FS=1 IT=392 TRAN CA=240 IS=1 FS=1 IT=392 FT=392. TT=900 FL=137.7 IP=1390 FP=955 TP=900 TP=900 TRAN CA=2 41 IS=1 FS=1 IT=392 FT=392 TT=900 FL=137.7 IP=955 FP=1025 IP=1025 FP=1025 TP=60 TRAN CA=242 IS=1 FS=1 IT=I00 FT=125 TT=60 FL=100 TP=210 TRAN CA=243 IS=1 FS=1 IT=125 FT=150 TT=210 FL=100 IP=1025 FP=1025 PAIR CA=201 i CO=27.,6 DI=0.521 EX=6. 4 Tavg=85 PAIR Tavg=100
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| * CO=27.6 DI=0. 512 EX=6.4 PAIR CA=202 Tavg=125 CA=203 CO=27.6 DI=0. 504 EX=6.4 PAIR Tavg=125 CA=204 CO*27.6 DI=0.504 EX=6.4 PAIR Tavg=180 CA=205 CO=27.6 D}}
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