attachment 3, stp units 3 & 4 - flow induced vibration ...(frp/fst) = i a,b * this is close...
TRANSCRIPT
U7-C-NINA-NRC- 120026
Attachment 3
STP Units 3&4 - Flow Induced Vibration - Chapter 3.9(Non-Proprietary)
STP Units 3&4 - Flow Induced Vibration -Chapter 3.9 (Non-Proprietary)
Westinghouse Non-Proprietary Class 3
U7-C-NINA-NRC- 120026Attachment 3
WEC-NINA-2012-0025 NP-Enclosure
STP Units 3 & 4
Flow Induced VibrationChapter 3.9
March 2012
Westinghouse Electric Company1000 Westinghouse Drive
Cranberry Township, PA 16066
©2012 Westinghouse Electric Company LLCAll Rights Reserved
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NRC M.eeting
March 29, 2012
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Agenda
" Introductions I Attendees" Desired outcomes
* Topics for Discussion- Pump Forcing Functions
* Outstanding Items- WCAP revisions, COLA revision (including ABAQUS)
* Wrap up, action items
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Attendees
© 2012 Westinghouse Electric Company LLC. All Rights Reserved.
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NINA" Scott Head" Tom Daley
" John Price
Morgan Lewis* Al Gutterman
Westinghouse* Brad Maurer" Dick Schwirian* Bob Quinn
TANE* Dale Wuokko
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Desired Outcomes
• Address appropriateness of pump induced pulsation forcing •function amplitude
" Summarize WCAP revisions to incorporate changes basedon RAIs and audits
" Preview COLA changes- Address computer code list in COLA w.r.t ABAQUS- Incorporate WCAP references
* Agree on next step(s) and action items
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Pump Forcing Functions
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Pump Forcing Functions
" Discussion of approach using RJ-ABWR data- Basis for selection of analysis case- Results based on use of RJ-ABWR data
* Confirmation using pump testing done for a reference pump "
- Vertical single stage pump- Single pump tests removes variable of phasing- Summary of ABWR and reference pump characteristics- Use of pump affinity relationships for scaling- Results
- Comparison to RJ-ABWR based results C
" Conclusions
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RJ-ABWR Data Interpretation
Sa,b,c
* [ ]a~,b,cThis is consistent with open-open modes starting at the steam-water interface inthe downcomer and ending at the steam-water interface above the core exit, adistance L of approximately 80 feet. (First mode frequency f = C/2L =.5*3200/80 = 20 HZ).
* The mode shapes for these modes are axial. Therefore, they would be mostsensitive to excitation from axial gradients in pressure amplitude.
SPump phasing is not known.-[]a,b,c Given the axial nature of the >
dominant modes, an all-pumps-in-phase model was used as a reasonable basis •to estimate the forcing function amplitudes.
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Pump Forcing Function Estimation:RJ-ABWR Data Based
Step 1: A 1.0 psi forcing function is applied to all 10 pumps and used tocalculate the pressure amplitude Pcalc at the P6 location.
Step 2: The RJ-ABWR value at [ ]a,b,c (Pmeas) is substituted for the measuredamplitude at [
] a,b,c
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Step 3: The forcing function pressure amplitude Pff is then calculated from
- Pff = (Pmeas/Pcalc)*1.0 = (Pmeas/Pcalc)
Step 4: The Pff value from step 3 is then adjusted for the operating conditions(density and speed) to be analyzed. The results for normal, full flow operatingconditions are:
a,c- Pff-RJ(1 per revolution) =
- Pff-RJ (2 per revolution) =
- Pff-RJ (blade passing)
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Pump Forcing Function Estimation:Single Pump Test Based
" Pump forcing functions have been independentlydetermined from single pump scale model testing
" To determine full scale forcing functions from scale modeltest data, pump affinity relationships were used.
- In particular, the pump forcing functions were taken to beproportional to the dynamic pressure at the impeller tip.
- This is proportional to the product of fluid density and the square ofthe product of impeller diameter and shaft rotational speed.
" The same scaling approach can also be used to estimate ý4 >Zthe STP-3 pump forcing functions from the single pump testbased forcing functions
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Pump Affinity Relationships
* Dimensional Analysis of pumps and fans yields the followingrelationship for head H as a function of volume flow Q,rotational frequency w, impeller diameter D, and Reynoldsnumber Re.
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gH/(wD) 2 = F[Q/(wD 3), Re]
where g is the acceleration of gravity. In most cases,Reynolds number dependence is insignificant, so, in effect,
gH/(wD) 2 = F[Q/(wD 3)] (1)
gH = (wD) 2*F[Q/(wD3)] (2)
Recognizing that the pump pressure rise Pis equal to P = pgH, results in
P =gH =(coD)2*F[Q/(wD3)] (3)
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Pump Affinity Relationships (continued)
Recognizing that Q is proportional to Vax*D 2 , where Vax is
the axial fluid velocity, and that wD is twice the impeller tip .
velocity Vt, converts (3) to the following:P = pgH = p(Vt) 2*F[Vax/ Vt] (4) 0
• Thus, the pump or fan pressure rise is proportional to theproduct of a dynamic pressure term based on the impellertip velocity Vt and a function F of the dimensionlessparameter P3 = Vax/Vt that is related to the angle of attack ofthe impeller blades with respect to the incoming axial flow. >
• Equation 4 can be used to compare the performance of the !STP-3 pumps to the reference pump. For this comparison,the data in Table 1 are needed.
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ABWR and Reference Pump Data
Table 1 STP-3
Parameter
D(in.)
Head H (ft)
Flow (gpm)
Density p (lb/ft3)
Vt (fps)
Vax (fps)
Rotational Speed (HZ)
p*'V 2 (psi)
P(psi)
p*Vt2 ratio (RP/STP-3)
P ratio(RP/STP-3)
and Reference Pump
STP-3 / RJ-ABWR
[ ]~,b
107
3Q430
47.092
[ ]~ab
[ ]~ab
Parameters
Reference Pump (RP)
[ ]ab
365
78750
47.7676
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[[
a.b
a,b
24.17
[ ]a,b
34.992
29.8
a2b
121.078
[ ]a,b
3.460>C
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Pump Affinity Relationships (concluded)
Table I are* It will be noted that the p(Vt)2 and P ratios from
approximately the same ([ ]a,b and 3.460).Eq (4) and forming the ratio of PRP/PST gives
PRP/PST =([ p*Vt2 ] RP/[p*Vt2]ST)*(FRp/FST)
Table 1 areUsing
(5)
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3.460 = [ ]a,b *( FRp/FST)a,b(FRp/FST) = I
* This is close enough to unity that Equation 5 can beapproximated as
PRP/PST =([ p*Vt2 ] RP/[p*Vt2]ST) (6)
or, inverting:
PST/PRP =([ p*Vt2]ST/[p*Vt2 ] RP)
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0o(7)
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Application of Affinity Relationships to PumpPulsations
While the relationships leading to Eq (7) apply directly to steady-statepump pressures, it is reasonable to expect similar applicability tofluctuating pressures as well..-o
- As discussed in Simpson et al, these unsteady fluctuations are "associated withthe passage of the impeller blades over the static diffuser blades or volutecutwater."
- The rationale is that, given that tip dynamic pressure [P*Vt\2] magnitude is thedominant parameter governing pump pressure P, it would be expected that thefluctuations in this dynamic pressure caused by the abrupt interactions of rotor
and stator blades during impeller rotation would also be proportional to impellertip dynamic pressure.
- The proportionality constant might be'different, but Eq (7) should still hold, at >least in an approximate sense. That is,
dPsT/dPRP =([ p*Vt2]ST/[p*Vt2 ]Rp) (7') >
where dp refers pump fluctuating pressure amplitude, or forcing functionamplitude.
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Results of RP Single Pump Tests
RP forcing function pressure amplitudes are: I.a,c C
Pff (1 per revolution) CD
- Pff (2 per revolution)- Pff (blade passing)
* Applying the relationship in Eq (7') and the appropriatepump data results in the following single pump test pressureamplitudes for STP-3:- Pff-RP (1 per revolution) a,c
- Pff-RP (2 per revolution)
- Pff-RP (blade passing)
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Pump Forcing Functions -- Comparison
" RJ-ABWR based vs. pump test based forcing functions:
Pump Frequency Pff-RJ (psi) Pff-RP (psi) Ratio
1R ac
2RBlade passing
" The forcing function amplitudes calculated based on thesingle pump tests are bounded by the RJ-ABWR basedforcing functions (that were used in the STP-3 analysis) bya significant margin
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Pump Forcing Functions - Conclusions
" Using all pumps in phase with RJ-ABWR pressure results is j-a reasonable approach
" Single pump testing with appropriate scaling indicates thatthe RJ-ABWR based forcing functions are adequatelybounding
• Comparison of calculated strains to measured strains inRJ-ABWR indicate our results are reasonable
• Extensive operating experience of ABWRs in Japan since1996 without any problems provides evidence that pump >pulsations are not causing issues in ABWR plants
" WCAP-17370-P (MTI Plan) includes STP-3 start-up testingto confirm pump-induced pulsation forcing functions
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FIV-Related WCAP Revisions
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FIV-related WCAP Revisions
" WCAP revisions are needed to close out confirmatory items- Changes per RAI responses
- Changes per audit actions
" Other changes needed for consistency and clarity- Keep reference between reports consistent (correct revisions)
- Correct typographical errors and reference numbers
" Changes summarized on next slide
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WCAP Revisionsor No Reo Toi I Change
_1
WCAP-1 7256
WCAP-1 7257
STP-3 CVAP
STP-4 CVAP
WCAP-17369 'OE
_WCAP-1 7370 MTI Plan
" Revise reference revisions
* Revise visual inspection requirements from VT-3 toVT-1 and revise associated text
* Correct reference numbers" Revise reference revisions
No changes required~~~_
* Revise pre-op test measurement uncertaintydescription
* Revise reference revisions
" Add statement that ACSTIC2 is only used for loads.on submergedstructures
" Remove statement regarding [1a b
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WCAP-1 7371 Non-dryer
* Correct typographical errors- Revise reference revisions
WCAP-1 7385 Steam Dryer * Add description of assessment for non-full pen weldsRevise reference revisions
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STP 3&4 COLA Revisions
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STP 3&4 COLA Revisions
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" STP 3&4 COLA Section 3.9.8 includes references to thetwo comprehensive vibration assessment program reports 0
- 3.9-13: WCAP-1 7256 (STP-3 CVAP Report)
- 3.9-14: WCAP-17257 (STP-4 CVAP Report)
" These two CVAP reports reference the other four FIVrelated reports, all of which are docketed
" NINA believes this approach adequately documents the >STP 3&4 FIV reports C z
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STP 3&4 COLA Revisions (continued)
" Addition of ABAQUS computer code (used for structuralanalyses of some STP 3&4 submerged structures)- Reference in Appendix 3D Section 3D.3
- Add to Section 4.1.4.1 and new Section 4.1.4.1.11 with codedescription
" Will be added in COLA R8- Suggested changes as shown on following slides
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STP 3&4 COLA Revisions (continued)
3D Computer Programs Used in the Design of Components, Equipment andStructures
The information in this appendix of the reference ABWR DCD, including allsubsections, is incorporated by reference with the following supplement. AkGComputer codes that isare used for analysis of reactor internal components is,are added to Section 3D.3.
3D.3 Reactor Pressure Vessel and Internals
The following computer programs are used in the analysis of the reactorpressure vessel, core support structures, and other safety class reactorinternals: NASTRO4V, SAP4G07, HEATER, FATIGUE, ANSYS, CLAPS,ASSIST, SEISM03 AND SASSI, and ACSTIC2, and ABAQUS. Theseprograms are described in Subsection 4.1.4. >
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STP 3&4 COLA Revisions (continued)
4.0 Reactor 4.1 Summary Description
The information in this section of the reference ABWR DCD, including all subsections and •figures, is incorporated by reference with the following supplement.ý Cmputer codes'",that isare used for analysis of reactor internal components isare. added to Section 4.1.4.1.
4.1.4.1 Reactor Internal Components
Computer codes used for the analysis of the internal components are as follows:
(11) ABAQUS;
4.1.4.1.11 ABAQUS
ABAQUS solves traditional implicit finite element analyses, such as static, dynamic, andthermal, all powered with a wide range of contact and nonlinear material options.ABAQUS also has optional add-on and interface products that address design sensitivity !ianalysis. ABAQUS enables a wide range of linear and nonlinear en.qineering simulations.:The computer code is used to perform modal analyses of various reactor internalcomponents.-
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Wrap up
* Action Items
* Schedule* Next actions
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