ML13051A193

Enclosure 5, L5-04GA585, Rev. 2, Analytical Evaluations for Operational Assessment

ML13051A193
Person / Time
Site:	San Onofre
Issue date:	02/18/2013
From:	Mitsubishi Heavy Industries, Ltd
To:	Office of Nuclear Reactor Regulation
References
TAC ME9727 L5-04GA585, Rev 2, SO23-617-1-M1543, Rev 0
Download: ML13051A193 (86)

Text

ENCLOSURE 5 MHI Non-Proprietary Document L5-04GA585, Analytical Evaluations for Operational Assessment (Non-Proprietary)

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San Onofre Nuclear Generatin! Station, Unit 2 & 3 REPLACEMENT STEAM GENERATORS Analytical Evaluations for Operational Assessment Supplier Status Stamp p"' S023-617-1-M1543 IR, fN/A 0 0DESIGNDOCIYIENT ORDER NO. R10R7.4RR MREFERENCE DOCUMENT-INFORMATION ONLY EMRP IOM MANUAL MFG MAY PROCEED: EDYES ONO IWA STATUS - A sMa isrequired fbr demn *domnts wd Isoptional for refWeee documna. Drwanga e ramvwlmd ed appmved for wmngmnt and owaomanrm to qpdlu oty. ApprM do"ss not res subnfr trnm do MrpOn*aRy of S uebly of desi, rot.rIle, sndtw *equpmen mefste.

r-. APPROVED APPROVEDEXCEPT AS NOTED.- MekeheM "anwd resuwnt

.NOTAPPROV tED- and moubli* for meve. NQT for fld uWe.

Cmt FLM Onw.

K MCE DE(i23) 6 REV. 3 07/tI REFERENCE 80123-XXIV-37.8.26 Purchabse Order No, 4500024051

-1 Specification No. S023-617-01R3 CONTENT REMARKS ORDER No. DATE Nuclear Plant Component PURCHASER Designing Department

[PAUB ITEM No. REENCB Steam Generator Designing Section ME-dio 2591012 APPIIOVE BY CH1ECM D Y IDTfAL 85 PAMI (MNES) 1lo0 DESIGNED BY ZI77;~DRAWN BY

[ ISSU DATE jTT TT~lF VFDWG.No. Rev .No.

IIHHH~1~L5-04GA5852 11 ____2 MIT9'*91USZUK1&(

M ISDUURZI,, LTD.

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Revision History Document No.L5-04GA585 No Revision Date Approved Checked] Prepared 0 Initial issue See cover sheet 1 -Revised stability ratios and pinning forces due to the change of stabilizer type.

-Revised the results of full bundle analyses due to change the input values of manufacturing dispersion.

2 -Revised in accordance with SCE comments of RSG-SCE/MHI-12-5782.

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Table of Contents

1. Purpose ................................................................................................................. 4

2. Sum m ary .......................................................................................................................... 4

3. Methodology of O perational Assessm ent ..................................................................... 5

4. MHI Scope of Supply for O perational Assessm ent .......................................................... 7

5. Definitions of 4 Categories and Selection of Representative Tube ............................... 8 5.1. Definitions of 4 Categories ........................................................................................ 8 5.2 Selection of representative tubes ............................................................................... 10

6. Force to Prevent In-Plane FEI ...................................................................................... 12 6.1. Purpose .......................................................................................................................... 12 6.2. Conclusion ..................................................................................................................... 12 6.3. Assum ption .................................................................................................................... 15 6.4. Acceptance criteria ................................................................................................... 16 6.5. Design inputs ................................................................................................................. 16 6.6. Methodology ................................................................................................................... 22 6.7 Results ............................................................................................................................ 24

7. Stability Ratio Boundary M ap ...................................................................................... 32 7.1. Methodology of Preparing Stability Ratio Boundary Map ........................................ 32 7.2. AVB Support Conditions .......................................................................................... 36 7.3. Stability Ratio Boundary Map ................................................................................... 42

8. Full Bundle Analyses ................................................................................................... 53 8.1. Purpose .......................................................................................................................... 53 8.2. Conclusions .................................................................................................................... 53 8.3. Acceptance Criteria .................................................................................................. 53 8.4. Assum ption .................................................................................................................... 53 8.5. Methodology ................................................................................................................... 54 8.6. Design Inputs ................................................................................................................. 56 8.7. Analysis results ........................................................................................................ 60

9. Reference ........................................................................................................................ 64 Case study of Representative Tubes for Evaluation of Force to Prevent In-Plane FEI ............................................................................................... 65 Case study of Methodology to Calculate Force to Prevent In-Plane FEI ...... 69 Influence of a tube at Stay Rod address on Contact forces in the Full Bundle

......................................................................................................................... 71 Attachm ent-4 Verification of the Q uarter Full Bundle Model ........................................... 80 MITSUBISHI HEAVY INDUSTRIES, LTD.

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1. Purpose The purpose of this document is to provide the analytical data to be used for the operational assessment of SONGS Unit-2 RSGs in order to return them to service. Unit-2 A-SG(2E089) is used for the analysis since it was the worst case of Unit RSGs (TTW) but that it will be applied to A the operational assessment for all Unit 2 RSGs to return to service. The data are inputs for the probability evaluation of in-plane fluid elastic instability (FEI) of the tubes in the next cycle performed by AREVA (Reference 22).

2. Summary The results of the activities performed by MHI are summarized as follows; (1) Definitions of 4 Categories and Selection of Representation Tube Tubes which have AVB wear indications are categorized into 4 categories and a representative tube for each category is selected as described in Section 5.

(2) Pinning force toPrevent In-Plane FEI The contact force sufficient to activate the AVB support points for in-plane direction in order to A prevent in-plane FEI are evaluated as described in Section 6.

(3) Stability Ratio Boundary Map In order to determine the supporting condition when in-plane FEI occur, the stability ratios (SR) of all tubes at various supporting conditions are calculated and the boundary maps are prepared as described in Section 7.

(4) Full Bundle Analyses The contact forces at each AVB support point of all tubes are calculated by using a complete FEM model of the tube bundle to judge whether each AVB support is active or not as described in Section 8.

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3. Methodology of Operational Assessment Fig.3-1 shows the evaluation flow chart of operational assessment, which is developed by AREVA (Reference 22) through the discussion with MHI. In order to carry out the return to service of SONGS Unit-2, the probability of in-plane FEI shall be less than 5% in the next cycle. The operational power level and operating period of next cycle is determined based on the in-plane A FEI probability evaluation.

The tubes which have wear indications are divided into separated categories and a representative tube of each category, which is the tube with the highest in-plane stability ratio in the category, is conservatively selected to evaluate the pinning forces..

For the representative tubes, the pinning forces ample to activate the AVB support points for in-plane direction in order to prevent in-plane FEI are evaluated to be used as criteria to judge whether an AVB support point is active or inactive.

By using a complete model of the tube bundle, the contact forces at tubes-to-AVBs contact points in all tubes are calculated. Based on the criteria of contact force of inactive supports, the probabilities of inactive supports are estimated.

The stability ratios (SR) of all tubes at various supporting conditions are calculated to prepare the boundary maps, which are used to determine the supporting conditions when in-plane FEI occur.

Based on the probabilities of inactive supports and the stability ratio boundary maps, the probability of in-plane FEI is obtained.

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Aý Determination of Methodology and Scope of Activities MIH'sscope I{

AR EVA'ssoe E Definition of Categories and Selection of Representative Tubes (Refer to Section 4) 4, I

Probability of contact force obtained by full bundle analyses at various operating periods (Refer to Section 8) ii Force to Prevent In-Plane FEI L - at various power levels (Refer to Section 6)

====!j Evaluation of the probability of the number of consecutive inactive AVB supports r,

Stability Ratio Boundary Map at various power levels (Refer to Section 7)

U Evaluation of the probability of in-plane FEI Determination of Power Level and Operating Period Fig.3-1 Evaluation Flow Chart of Operational Assessment IA MITSUBISHI HEAVY INDUSTRIES, LTD.

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Document No. L5-04GA585(2) iiAw

4. MHI Scope of Supply for Operational Assessment As shown in Fig.3-1, MHI performed the following activities for the operational assessment as required by AREVA.

Definitions of 4 Categories and Selection of Representation Tube See Section 5 Force to Prevent In-Plane FEI See Section 6 Stability Ratio Boundary Map See Section 7 Full Bundle Analyses and Bench Marking Studies See Section 8 These results are inputs for the probability evaluation of in-plane fluid elastic instability (FEI) of the tubes in the next cycle performed by AREVA.

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5. Definitions of 4 Categories and Selection of Representative Tube 5.1. Definitions of 4 Categories The tubes of Unit-2A (E089), which have tube-to-tube wear and AVB wear indications, are categorized into 4 categories as follows. The addresses of the 4 categories are shown in Fig.5.1-1.

(1) Plugged tubes which have tube-to-tube wear (TTW) indications: 2 tubes (2) Plugged tubes which have AVB wear indications: 209 tubes (3) Unplugged tubes which have AVB wear indications in the center columns (Col.40-138): 554 tubes (4) Unplugged tubes which have AVB wear indications in the peripheral columns (Col.1-39 and 139-177): 39 tubes The tubes adjacent to the retainer bars and tubes which have wear indications at only the tube support plate elevations are not taken into consideration.

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141 136 131 QCstspry IiTT 126 xcaemqr 2: Pkqmod 121 116 00ateaorv 3: Wea (AVS or AVS-TSP) (CoLO4-138) 111 00satgor 4: Wea (AVBor AVB÷TSP) (Co1,-39. I39-17) 106 O~lwessn~twte tub*%for CA 101 x~kkaed ORB) 97 91 86 m1 66 61 56 51 46 41 36 31 26 21 0 16 0 11 0 6

3 H

CD COL 5.

aO 0

Fig.5.1-1 Definitions of Categories Ca SCA c~

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5.2 Selection of representative tubes The tubes listed in Table 5.2-1 are selected as representatives, which stability ratios of in-plane FEI with 12 consecutive inactive support points are the maximum in each of the four categories when the thermal power is 70%. Fig.5.2-1 shows the stability ratio map with 12 consecutive inactive support points when the thermal power is 70%. This map is prepared by calculating the stability ratios of 306 representative tubes and the stability ratios of the tubes which were not analyzed were obtained by interpolation method (See Section 7 for detail). A tube map of the 306 representative tubes is shown later as Figure 7.1-2.

Table 5.2-1 Representative tubes Row Column Stability Ratio (1) Plugged tubes with TTW 113 81 F" "

(2) Plugged tubes with AVB wear 97 89 (3) Unplugged tubes with AVB wear 98* 90*

in center columns (4) Unplugged tubes with AVB wear 70 164 in peripheral columns I I "

Note *)

• The stability ratios of the tubes which are not analyzed are assumed by interpolation method.

Therefore, there is a possibility that a tube with an interpolated stability ratio value in the critical region may have a higher stability ratio than the selected representative tube because interpolated value always calculated lower than the analyzed value. In order to address this _A inconsistency, a detailed analysis for each tube in the critical region is performed to find out the stability ratio of each tube. From the analysis result, we found out that the tube in Row 96 Column 90 has a slightly (2.2%) higher stability ratio than the tube in Row 98 Column 90, which is the I-representative tube. However, the impact is very small since these 2 tubes are next to each other and the flow condition is almost identical. Therefore, Row 98 Column 90 is evaluated as a representative. As for other representative tubes, the selected tubes for each category have higher stability ratios than the rest of the tubes in the same category.

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(n C

W C

(1)

-I M

Sn 0Z 0 0 0

0 CD CD 0) 0ý MD 00 Fig.5.2-1 In-plane SR mapping with 12 consecutive inactive support points when the thermal power is 70%

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6. Force to Prevent In-plane motion 6.1. Purpose 1A The purpose of this evaluation is to obtain the contact force ample to activate the AVB support points for in-plane direction in order to prevent in-plane FEI.

Ri 9 CnnrnhIminn The criteria of the force to prevent the in-plane motion of representative tubes are evaluated as A shown in Table 6.2-1 to 6.2.4.

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JAW Table 6.2-1 Summary of Required Contact Forces for 60% Thermal Power I&

Unit: N Category Representative 801 B02 B03 B04 B05 B06 B07 B08 B09 B10 Bl B12 tubes 1 R113 C81" __

2 R97 C89*

3 R98 C90 __

4 R70 C164 Evaluation is not needed since the stability ratio is less than 1.0 even if all AVB support points are inactive. (See Section 7 for detail)

Note)*: Plugged with Type J stabilizer (split stabilizer)

Table 6.2-2 Summary of Required Contact Forces for 70% Thermal Power Unit: N Category Representative B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 B1l B12 tubes I R113 C81" 2 R97 C89" 3 R98 C90 _ -_

4 R70 C164 Evaluation is not needed since the stability ratio is less than 1.0 even if all AVB support points are inactive. (See Section 7 for detail)

Note)*: Plugged with Type J stabilizer (split stabilizer)

Table 6.2-3 Summary of Required Contact Forces for 80% Thermal Power Unit: N Category Representative B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 tubes 1 R113 C81* r 2 R97 C89-3 R98 C90 _. _

4 R70 C164 Evaluation is not needed since the stability ratio is less than 1.0 even if all AVB I support points are inactive.(See Section 7 for detail)

Note)*: Plugged with Type J stabilizer (split stabilizer)

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Table 6.2-4 Summary of Required Contact Forces for 100% Thermal Power

/Unit: N Category Representative B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 tubes 1 R113 C81 2 R97 C89 3 R98 C90 _

4 R70 C164 Evaluation is not needed since the stability ratio is less than 1.0 even if all AVB support points are inactive.(See Section 7 for detail)

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Ak 6.3. Assumption (1) Fluid force The turbulent excitation force is evaluated and fluid force caused by FEI is not taken into account due to the following reason.

The purpose of this evaluation is to obtain the contact force ample to activate the AVB support points JA for in-plane direction in order to prevent in-plane motion.

When the friction force due to contact force is smaller than the turbulent excitation force at an AVB support point, a tube can slide in the in-plane direction. In-plane motion could occur when the tube JA slides at some AVB support points.

However, if the stability ratio (SR), which is calculated by assuming AVB support points where the tube slides are inactive, is less than 1.0, in-plane FEI will not occur. 2A For example, SR of a tube is smaller than 1.0 when only 2 support points (B111 and B12) are active while the remaining 10 support points (801 to B10) are inactive.In this case, if the contact forces at Bll and B12 are the same or greater than the force ample to resist against the turbulent force, in-plane FEI will not occur. A (2) Number of inactive support points The calculation is performed by assuming that one AVB support point is pinned (with spring element) and other AVB support points are free (with gap in the out-of-plane direction) in order; (i) To obtain a force ample to resist against the turbulent excitation force with a higher value than the actual condition with more than 1 active support point and, A (ii) To simplify the evaluation of the force since there are too many possible combinations of inactive support points for the evaluation that can be taken into account.

(3) Representative tubes The representative tubes for Category 1 to 3 (R1 13 C81 for Category 1, R97 C89 for Category 2 and R98 C90 for Category 3) are evaluated.

The stability ratio of R70 C164 (representative of Category 4) is less than 1.0 even if all AVB support points are inactive. Consequently, there is no probability of in-plane motion in Category 4 and no --

need to evaluate the pinning force for Category 4.

In order to evaluate the sensitivity of the tube location, additional 2 tubes (Row 131 Column 89 and Row 81 Column 89, which are selected by AREVA) are evaluated as shown in Attachement-1.

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Document No. L5-04GA585(2) 6.4. Acceptance criteria There is no acceptance criterion because the purpose of this evaluation is to determine the contact JA force ample to prevent in-plane motion.

6.5. Design inputs 6.5.1 Geometry The tube bundle consists of %-inch diameter, thermally treated Alloy 690 U-tubes that are arranged in a 1.0-inch equilateral triangular pitch and are supported by the tubesheet, seven tube support plates, and six sets of anti-vibration bars (AVBs). Tube support plates (TSPs) have broached trifoil tube holes. All the contacting support structures above the tubesheet are made of 405 stainless steel.

The nominal dimension of tube, TSPs and AVBs are listed in Table 6.5-1.

6.5.2 Thermal and Hydraulic flow of steam generator secondary side The ATHOS thermal hydraulic analysis program was used to determine the distributions of fluid gap velocity in the normal direction to tube in-plane and fluid density as the inputs for vibration analysis (See Reference 1 for detail). Fig 6.5-1, Fig.6.5-2, Fig.6.5-3 and Fig.6.5-4 show the flow characteristics at 60%, 70%, 80% and 100% thermal power those are applied to the tubes for the IJA evaluation.

6.5.3 Damping ratio The damping ratio used for this evaluation is obtained by the same calculation as specified in IA Reference 1.

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Table 6.5-1 Nominal dimensions of tubes, TSPs, and AVBs Part Item Value Material Thermally treated SB-1 63 UNS N06690 Outside diameter 0.75 in Thickness 0.043 in Tubes Number of tubes 9727 Tube pitch 1.0 in Tube arrangement Triangular Material Thickness TSPs Number of TSPs Tube support span (between TSP centers)

Tube support span (from tubesheet to TSP-1)

Material Type AVBs Thickness Width MITSUBISHI HEAVY INDUSTRIES, LTD.

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/0ý J

(a) Flow Velocity (b) Flow density Rowl13 Col8l (a) Flow Velocity (b) Flow density Row97 Col89

-1 (a) Flow Velocity (b) Flow density Row98 Col90 Fig. 6.5-1 Flow Characteristics at 60% Thermal Power MITSUBISHI HEAVY INDUSTRIES, LTD.

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(a) Flow Velocity (b) Flow density Rowl13 Col8l (a) Flow Velocity (b) Flow density Row97 Col89 (a) Flow Velocity (b) Flow density Row98 Col90 Fig. 6.5-2 Flow Characteristics at 70% Thermal Power MITSUBISHI HEAVY INDUSTRIES, LTD.

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JAW K

\I (a) Flow Velocity Rowi 13 Col8l (b) Flow density J

r (a) Flow Velocity (b) Flow density Row97 Col89 (a) Flow Velocity (b) Flow density Row98 Col90 Fig. 6.5-3 Flow Characteristics at 80% Thermal Power MITSUBISHI HEAVY INDUSTRIES, LTD.

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\I-(a) Flow Velocity (b) Flow density Rowl13 Col8l

-I (a) Flow Velocity (b) Flow density Row97 Col89 K

(a) Flow Velocity (b) Flow density Row98 Col90 Fig. 6.5-4 Flow Characteristics at 100% Thermal Power MITSUBISHI HEAVY INDUSTRIES, LTD.

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Document No. L5-04GA585(2) 6.6. Methodology All TSP points are modeled to be pinned and the selected AVB support is modeled as the spring element to obtain the reaction force at the selected AVB support. As shown in Table 6-1, 12 cases of 11 inactive support points are evaluated for each representative tube. The analysis model when B07 is active is shown in Fig.6.6-1.

The contact force needed to activate the AVB support function in-plane is calculated as follows.

(1) The reaction forces of tube subjected to random excitation (Reaction force of in-plane Fi and out-of-plane F,) are calculated F,= max{F.CT)+ F7(y)2}

Fo= max{Fj(t)}

(2)The contact force F,, which is sufficient to prevent slip motion by friction force is calculated as follows.

FC=F,/MU

Where, pu: Friction coefficient (3)By taking into account of contact force reduced by the reaction force F, in the out-of-plane direction, the required contact force, Freq, is derived by the equation below.

Freq= F,+F F0 This methodology is considered to be conservative since the maximum values both of in-plane and out-of-plane are summed. In order to evaluate the sensitivity of changing the evaluation method to calculate the double of standard deviation, the case study is performed as described in Attachment

-2.

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Table 6.6-1 Active/Inactive Support Points Evaluated point B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 B01 A I I I I I I I I I I I B02 I A I I I I I I I I I I B03 I I A I I I I I I I I I B04 I I I A I I I I I I I I B05 I I I I A I I I I I I I B06 I I I I I A I I I I I I B07 I I I I I I A I I I I I B08 I I I I I I I A I I I I B09 I I I I I I I I A I I I 810 I I I I I I I I I A I I B11 I I I I A I B12 I I I I I I I I I I I A A: Active support point I: Inactive support point Fig 6.6.1 Analysis model when B07 is active MITSUBISHI HEAVY INDUSTRIES, LTD.

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Document No. L5-04GA585(2) 6.7 Results The calculated contact forces are rounded up to be integral numbers as shown below.

6.7.1 60% Thermal Power The analysis results at 60% thermal power are shown in Table 6.7.1-1 to 6.7.1-3.

Table 6.7.1-1 Required contact force of R113 C81 (with Type J stabilizer)

Unit:N Evaluated point B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 311 B12 1301 __

B02 B03 B04 B05 B06 B07 B08 B09 B10 811 _ _ _ _ _ _ _ _ _ _

B12 " ._

1:Inactive support point MITSUBISHI HEAVY INDUSTRIES, LTD.

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Ak Table 6.7.1-2 Required contact force of R97 C89 (with Type J stabilizer)

Unit:N Evaluated point BO1 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 1301 S""

B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 -_

I: Inactive support point Table 6.7.1-3 Required contact force of R98 C90 Unit:N Evaluated point B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 311 B12 B01 /00-B02 B03 B04 B05 B06 B07 B08 B09 B10 811 _ _ _ _ _ _ _ _ _ _

B12 _ -

I: Inactive support point MITSUBISHI HEAVY INDUSTRIES, LTD.

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Document No. L5-04GA585(2) 6.7.2 70% Thermal Power The analysis results at 70% thermal power are shown in Table 6.7.2-1 to 6.7.2-3.

Table 6.7.2-1 Required contact force of R1 13 C81 (with Type J stabilizer)

Unit:N Evaluated point B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 1301 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 _"

I: Inactive support point Table 6.7.2-2 Required contact force of R97 C89 (with Type J stabilizer)

Unit:N Evaluated point B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 801 /01- __ __

B02 B03 B04 B05 B06 B07 B08 B09 B10 811 __

B12 1:Inactive support point MITSUBISHI HEAVY INDUSTRIES, LTD.

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Ai i Table 6.7.2-3 Required contact force of R98 C90 Unit:N Evaluated point B01 B02 B03 B04 B05 B06 B07 B08 B09 B1O B11 B12 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 _ _

I: Inactive support point MITSUBISHI HEAVY INDUSTRIES, LTD.

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Ak 6.7.3 80% Thermal Power The analysis results at 80% thermal power are shown in Table 6.7.3-1 to 6.7.3-3.

Table 6.7.3-1 Required contact force of R1 13 C81 (with Type J stabilizer)

Unit:N Evaluated point B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 Bll B12 B01 B02 B03 B04 B05 B06 B07 B08 B09 810 B12 _ '

I: Inactive support point Table 6.7.3-2 Required contact force of R97 C89 (with Type J stabilizer)

Unit:N Evaluated point B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 801 B02 803 B04 B05 B06 B07 B08 B09 B10 811_____

B12 I Inactive support point MITSUBISHI HEAVY INDUSTRIES, LTD.

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Table 6.7.3-3 Required contact force of R98 C90 Unit:N 1301 Evaluated point 801 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 B12 B02 B03 B04 B05 B06 B07 B08 B09 810 811 __

B12 1: Inactive support point MITSUBISHI HEAVY INDUSTRIES, LTD.

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Ak 6.7.4 100% Thermal Power (with no plugging)

The analysis results at 100% thermal power (with no plugging) are shown in Table 6.7.4-1 to 6.7.4-3.

Table 6.7.4-1 Required contact force of R1 13 C81 Unit:N Evaluated point 801 B02 B03 B04 B05 B06 B07 B08 B 09 B10 Bll B12 8101 / "

B02 B03 B04 B05 B06 B07 B08 B09 B10 B12 I: Inactive support point Table 6.7.4-2 Required contact force of R97 C89 Unit:N Evaluated point 801 B02 B03 B04 B05 B06 B07 B08 B09 B10 811 B12 B02 B03 B04 B05 B06 B07 B08 B09 B10 811 _ _ _ _ _ _

B12 __" -.

I: Inactive support point MITSUBISHI HEAVY INDUSTRIES, LTD.

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Ak Table 6.7.4-3 Required contact force of R98 C90 Unit:N Evaluatedpoint B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 Bl B12 8301 B02 B03 B04 B05 B06 B07 B08 B09 B10 B11 \

B12 I T -

1:Inactive support point MITSUBISHI HEAVY INDUSTRIES, LTD.

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-At

7. Stability Ratio Boundary Map 7.1. Methodology of Preparing Stability Ratio Boundary Map The methodology of calculating the stability ratios against in-plane FEI is described in Reference 1.

As shown in Fig.7.1-1, 9422 tubes are not to be plugged, 211 tubes are to be plugged with the type J stabilizers (0.5" OD, split stabilizer), 15 tubes are to be plugged with the standard stabilizers and 79 tubes are to be plugged without stabilizers for Cycle 17 operation of Unit-2A (E089) SG. Based on the stability ratio calculation results of the representative tubes, the stability ratios of all tube are obtained by the interpolating method as follows.

O:Tube Plugge With Typ J Ost*w

• Tube plugged with stndarW outsbifer Row-t4l Row-13 - ---- _

Row-31 Row-120 Row-121 Row-Il1l Row-t 06 Row-101 Row-96 Row-91 Rw-8 I Row-76 Row-71 Row-"6 Row-61 Row-%6 Row-5t Row-411 ROw-41 Row-36 ROw-31 R~w-21 Row-6 Raw-l X

Fig.7.1-1 Plugged Tubes MITSUBISHI HEAVY INDUSTRIES, LTD.

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(1) Unplugged tubes In order to prepare the maps, the stability ratios are calculated for the representative ( )tubes as shown in Fig.7.1-2, which are selected for every 4 rows and 4 columns in the outer row region and for every 8 rows and 8 columns in the remaining region. The stability ratios of tubes which are not analyzed are assumed by interpolation method to obtain the stability ratios of all tubes (9727 tubes).

For 100% thermal power condition, all tubes are assumed to be unplugged to simulate the stability ratios in Cycle 16.

-I Fig.7.1-2 Representative 306 Tubes to obtain SRs of all tubes MITSUBISHI HEAVY INDUSTRIES, LTD.

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At (2) Plugged tubes For the cases of 60%, 70% and 80% thermal power conditions, the stability ratio of plugged tubes are obtained as follows.

Plugged tubes with Type J stabilizers (split stabilizer)

The stability ratios for 211 plugged tubes in Category-2 are also calculated by interpolating stability IA ratios of representative tubes. As shown in Fig.7.1-3, the stability ratios of C )representative tubes are calculated by assuming all of these ( ) tubes are plugged to obtain the stability ratios of 211 plugged tubes with Type J stabilizer (split stabilizer) by the interpolating method.

JA K

Fig.7.1-3 Representative 155 Tubes to obtain SRs of plugged tubes MITSUBISHI HEAVY INDUSTRIES, LTD.

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At Plugged tubes with standard stabilizers and without stabilizers The stability ratios of plugged tubes with standard stabilizers and plugged tubes without stabilizers are estimated based on the calculated stability ratios of unplugged tubes by taking into account of the effect of the additional mass of the stabilizer and the decrease of primary coolant mass on the natural frequency and damping as shown in the following equations.

mto'= m + ms + m/

MO =m, + MP +m,

Where, f Natural frequency of unplugged tube f Natural frequency of plugged tube m0 :Average mass per unit length of unplugged tube mo' :Average mass per unit length of plugged tube my :Virtual added mass per unit length mt Mass of tube metal per unit length ms :Mass of stabilizer per unit length*

MP :Mass of primary coolant in tube per unit length Note *) for plugged tube without stabilizer, the additional mass of stabilizer is not taken into account.

As described in Reference 1, the effect of void fraction on the squeeze film damping is not taken into account since plugged tube has no heat transfer.

MITSUBISHI HEAVY INDUSTRIES, LTD.

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Document No. L5-04GA585(2) 7.2. AVB Support Conditions The stability ratios at various supporting conditions are calculated to find the limitation of the number of inactive support points when the stability ratios exceed 1.0 for the evaluation of FEI probability.

The inactive support points are assumed to be biased in hot side since the stability ratios are higher than other conditions (e.g. symmetrical or concentrated in cold side).

(1) 60% thermal power IA The stability ratio boundary maps are not prepared since the stability ratios of all tubes are smaller than 1.0 even if 12 support points are inactive as shown in Fig.7.2-1.

However, the stability ratio data sets of all tubes for 10 to 12 consecutive inactive support conditions are prepared just in case.

(2) 70% thermal power JA The stability ratio boundary maps for the following 2 cases are prepared since the stability ratios of all tubes are smaller than 1.0 when 10 support points are inactive as shown in Fig.7.2-2. In addition, the stability ratio data sets of all tubes for 4 to 12 consecutive inactive support conditions are prepared in order to compare with the stability ratios at 100 % thermal conditions.

- 12 support points are inactive

- 11 support points are inactive (B12 is active)

(3) 80% thermal power IJA The stability ratio boundary maps for the following 4 cases are prepared since the stability ratios of all tubes are smaller than 1.0 when 8 support points are inactive as shown in Fig.7.2-3.

The stability ratio data sets of all tubes for 7 to 12 consecutive inactive support conditions are prepared just in case.

- 12 support points are inactive

- 11 support points are inactive (B12 is active)

- 10 support points are inactive (B131 and B12 are active)

- 9 support points are inactive (B10, B131and B132 are active)

MITSUBISHI HEAVY INDUSTRIES, LTD.

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(4) 100% thermal power (without plugging)

The stability ratio boundary maps for the following 8 cases are prepared since the stability ratios of all tubes are smaller than 1.0 when 4 support points are inactive as shown in Fig.7.2-4.

The stability ratio data sets of all tubes for 4 to 12 consecutive inactive support conditions are also prepared.

- 12 support points are inactive

- 11 support points are inactive (B12 is active)

- 10 support points are inactive (B131 and B12 are active)

- 9 support points are inactive (B10, B131 and B12 are active)

- 8 support points are inactive (B9, B10, B11 and B12 are active)

- 7 support points are inactive (B8, B9, B10, Bll and B12 are active)

- 6 support points are inactive (B7, B8, B9, B10, B131 and B12 are active)

- 5 support points are inactive (B6, B7, B8, B9, B10, Bll and B12 are active)

- 4 support points are inactive (B5, 86, B7, B8, B9, B10, 311 and B12 are active)

MITSUBISHI HEAVY INDUSTRIES, LTD.

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ic C

z0 0

,=

tCD C 5.

CO)

-I X

cn 0

0 0

C 3

CD z

0 Fig.7.2-1 Stability ratio distribution at 60% thermal power when all support points are inactive IA CO 01 Page 38 of 85 S023-617-1-M1543, REV. 0

CA 030 zz 00

> (0 CI-0 0

a 3

IA 01 Fig.7.2-2 Stability ratio distribution at 70% thermal power when 10 support points are inactive V (B 11 and B12 are active)

OD (

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-.I a

CO U) z 0

m 0 z

(/)

m 00 E33 C~CD CdCD I-O CD Fig.7.2-3 Stability ratio distribution at 80% thermal power when 8 support points are inactive *,o (B9, BIO, B1l and B12 are active) G)

CO o)

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CA FA- z 0

z CA =

C" M

--i 00 0

3 0

Fig.7.2-4 Stability ratio distribution at 100% thermal power when 4 support points are inactive i-*

z (B5, B6, B7, B8, B9, BIO, Bll. and B12 are active) CO 0:

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Ak 7.3. Stability Ratio Boundary Map As mentioned in Section 7.2, the stability ratio data set of all tubes in each condition is prepared as shown in Table 7.3-1, which are attached with this report.

Based on the stability ratio data, the stability ratio boundary maps are prepared as shown in Fig.7.3-1,7.3-2 for 70 % thermal power, Fig.7.3-3,7.3-4 for 80% thermal power and IA Fig.7.3-5,7.3-6 for 100% thermal power. The stability ratio boundary map for 60% thermal power condition is not prepared because all stability ratios at 60% thermal power condition are smaller than 1.0 even if all AVB support points are inactive as described in Section 7.2. Fig.7.3-2, 7.3-4 and 7.3-6 show the tubes of each category in addition to the SR boundaries. The color of each plot indicates the minimum number of inactive AVB support points, when the stability ratio is greater than 1.0. The distribution of color plots is not symmetrical because the stability ratios of the plugged tubes, which are distributed asymmetrically, are estimated as mentioned in Sec.7.1.

By using the boundary map of the minimum number of inactive support points when the stability ratio is greater than 1.0, the tubes of each category are categorized by multiple groups as shown in Table.7.3-2 for 60 % thermal power, Table.7.3-3 for 70% thermal power, Table 7.3-4 for 80% JA thermal power and Table 7.3-5 for 100% thermal power.

Table 7.3-1 Stability Ratio Data Set of All Tubes Number of inactive Thermal power File name 60%_ points 10 o2SQ011support 60% 10 to 12 SR Q60 12-10 inactive supports 20120905.xls 70 % 4 to 12 SRQ70_12-4_inactive supports_20120913.xls 80% 7 to 12 SR Q80 12-7 inactive supports 20120905.xls SR_Q100_with no plugging_12-4inactive 100s% 4 to 12 supports_20120710.xls MITSUBISHI HEAVY INDUSTRIES, LTD.

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-I C

w ca

= z 0

m

> 0 z

Co CA

-I DCD-Co m

I-P0 0

0 CD Fig.7.3-1 Stability ratio boundary map at 70% thermal power 0

G) o Page 43 of 85 S023-617-1-M1543, REV. 0

(n)

= z0 z

r-D m 0 C0 CA m3 0

z 0

Fig.7.3-2 Stability ratio boundary map at 70% thermal power and tubes of each category 00 Page 44 of 85 S023-617-1-M1543, REV. 0

co ca M z0 0

--I CD Mi 0, (0

0 0

0 CD M

Fig.7.3-3 Stability ratio boundary map at 80% thermal power OD- U Page 45 of 85 S023-617-1-M1543, REV. 0

C z0 0

CD CI M.

h. CD

3 I-Fig.7.3-4 Stability ratio boundary map at 80% thermal power and tubes of each category C:'

COi O0 0) 0' Page 46 of 85 S023-617-1-M1543, REV. 0

CI M,

z0 z 10 0

CO a,

0 0

CD 3

Fig.7.3-5 Stability ratio boundary map at 100% thermal power C)

I-D G) 0n 3:

OD 14.

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CO)

CO M z0 0

C CA

-1 M

CA CD OD0 Fig.7.3-6 Stability ratio boundary map at 100% thermal power and tubes of each category Page 48 of 85 S023-617-1-M1543, REV. 0

Table 7.3-2 Number of tubes in each group categorized by SR Boundary Map at 60% thermal power Category 1 Category 2 Category 3 Category 4 Group Number of Inactive support points Rat13ory1 R1 13 C81 R97egor R97 C89 R R98 090 C90 R R70 0164 C164 Probability of in-plane FEI 1 SR<1 when 12 AVB support points are inactive r"_"_

2 SR>1 when 12 support points are inactive Total (SR<1 when 10 AVB support points are inactive) ___

CD z0 M

0 Z

CD(D CD CO) rn 0,

0 G) 00 CO Page 49 of 85 S023-617-1-M1543, REV. 0

Table 7.3-3 Number of tubes in each group categorized by SR Boundary Map at 70% thermal power I&

Category 1 Category 2 Category 3 Category 4 Group Number of Inactive support points Rit13ory1 R97ego9y R9 CagC90 R R1 13 C81 R97 C89 R98 R70 0164 C164 Probability of in-plane FEI 1 SR1 when 12 support points are inactive 2

SR<1 when 11 consecutive support points are inactive CA SR>1 when 11 consecutive support points are inactive 3 SR<I when 10 consecutive support points are inactive 4 SRI when 10 consecutive support points are inactive z0 Total 0 (SR<I when 9 AVB support points are inactive) -_

CO (D

(n 01 01 3

G) 00 C1 00 CA Page 50 of 85 S023-617-1-M1543, REV. 0

Table 7.3-4 Number of tubes in each group categorized by SR Boundary Map at 80% thermal power Group Number of Inactive support points Ril13 C81 1 Category Category R97 089 2 Category R98 C90 3 R70 C1 4 Category Probability of in-plane FEI rbaiit6finpan4~

R points are inactive 1 SR<1 when 12 AVB support SR>1 when 12 support points are inactive 2 SR<1 when 11 consecutive support points are inactive SR>1 when 11 consecutive support points are CA inactive C 3 SR<1 when 10 consecutive support points are CA inactive SR>1 when 10 consecutive support points are z inactive 0 4 SR1 when 9 consecutive support points are C

inactive CO) 5 SR1 when 8 consecutive support points are 6 inactive Total 0D Total 0)

(SR<I when_7_AVB support points are inactive) __________ __________ ____________

C1

b. D 00 K') (.n Page 51 of 85 S023-617-1-M1543, REV. 0

Table 7.3-5 Number of tubes in each group categorized by SR Boundary Map at 100% thermal power Group Number of Inactive support points R1 13 C81 1 Category R97 C89 2 Category R98 C90 3 Category R70 C1644 Category Probability of in-plane EI 1 SR<1 when 12 AVB support points are inactive _

2 SR>1 when 12 support points are inactive 2___SR<1 when 11 consecutive support points are inactive 3 SR>1 when 11 consecutive support points are inactive 3__ISR<1 when 10 consecutive support points are inactive ic 4 SR>1 when 10 consecutive support points are inactive SR<1 when 9 consecutive support points are inactive 5 ISR>1 when 9 consecutive support points are inactive M I SR<1 when 8 consecutive support points are inactive z0 6 ISR>1 when 8 consecutive support points are inactive Z

6 SR<1 when 7 consecutive support points are inactive 0 XD 7 ISR>1 when 7 consecutive support points are inactive

, SR<1 when 6 consecutive support points are inactive M 8 ISR>1 when 6 consecutive support points are inactive 8 SR<1 when 5 consecutive support points are inactive _ 0ID 9 ISR>1 when 5 consecutive support points are inactive

, SR<1 when 4 consecutive support points are inactive 10 SR>1 when 4 consecutive support points are inactive Total (SR<1 when 4 AVB support points are inactive) 0 G)

U' C't 00 K)

O1 0

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,A

8. Full Bundle Analyses 8.1. Purpose The purpose of this section is to provide the full bundle analyses results in the following cases for the operational assessment of Unit-2 at Cycle 17 and benchmarking studies of Unit-2 and Unit-31_

at Cycle 16.

8.2. Conclusions The analyses for Unit-2 after additional 6 months are completed for calculation of in-plane FEI occurrence probability, and the analyses for both of Unit-2 and Unit-3 at BOL and cycle 17 are completed for benchmarking.

8.3. Acceptance Criteria There is no criterion for this calculation.

8.4. Assumption (1) The manufacturing dispersion of Unit-2 A-SG (E089) represents Unit-2, and Unit-3 A-SG(E089) represents Unit-3.

(2) The dimensional manufacturing tolerances are based on the actual measurement results.

The dimensions, which were not measured but checked by the go/no-go, are assumed based on the drawing tolerances and the AVB pressing test results for the calculated contact forces to be consistent with the ECT ding signals (See Appendix-9 of Reference 2 for details).

(3) Hydrodynamic pressure is neglected in this calculation because friction forces due to manufacturing tolerances are much higher than contact forces caused by hydraulic pressure.

Therefore, hydraulic pressure hardly displaces the tubes.

(4) Wear rates have no correlation with thermal power levels in this calculation because AVB wear is caused by random vibration and random vibration is supposed to be independent of thermal power level. Consequently, the wear rates at 17 cycle are assumed to be kept to the additional periods operation. And the contact forces are independent of thermal power level in this calculation.

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Ak 8.5. Methodology 8.5.1 Analysis model All parts of the U-bend assembly above the #6 TSP (Tubes, AVBs, Retaining bars, Retainer bars and Bridges) are modeled as beam elements(See Appendix-9 of Reference 2 for details).

Figure 8.5.1-1 shows overview of the analysis model. The analysis model used is a symmetrical quarter model (The validity of quarter model is shown in Attachment-4). The contact points between tube to AVB, and tube to TSP are modeled as gap elements, which show spring property in compression. Stayrod is modeled as tube since the effect of this modeling is negligibly small as shown in Attachment-3.

L.

Bird's-eye View of the Model Front View of the Model Fig.8.5.1-1 Analysis model M[TrSUBISHI EAV INDUSTRE*SI, LTD.

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Ak 8.5.2 Analysis cases The analysis cases shown in Tab.8.5.2-1 are performed for the operational assessment of Unit-2 and benchmarking studies for Unit-2 and Unit-3.

Table 8.5.2-1 Analysis cases Cycle 16 17 Purpose Bench marking studies Operational Assessment Operation Beginning 3 months 12 months End 6 months 12 months period Condition Cold Hot Hot Hot Hot Hot Hot Unit-2 5-9-259 5-9-261 - 5-9-265 5-9-269 5-9-273 5-9-297 E089 5-9-262 5-9-266 5-9-270 5-9-274 5-9-298 5-9-263 5-9-267 5-9-271 5-9-275 5-9-299 5-9-264 5-9-268 5-9-272 5-9-276 5-9-300 Unit-3 5-9-306 5-9-309 5-9-307 - 5-9-308 - -

E089 5-9-311 5-9-312 5-9-313 A 5-9-314 5-9-315 5-9-316 1 1 5-9-317 5-9-318 1 5-9-319 MITSUBISHI HEAVY INDUSTRIES, LTD.

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Ak 8.6. Design Inputs 8.6.1 Geometry and manufacturing dispersion The nominal tube and tube support dimensions are obtained from the design drawings (Reference 3 to 20). The manufacturing dimensional tolerance dispersions of Tube G value, tube pitch, tube flatness, AVB thickness deviation, AVB twist, and AVB flatness are considered in the analysis model. The deviation is generated according to random number and inputted to the gap elements in the analysis model. The random number dispersion follows normal distribution.

Table 8.6.1-1 shows input of manufacturing dispersion to the analysis model.

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Ak Table 8.6.1-1 Measurement results of the dimensions

/11ý-

I\',

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Document No. L5-04GA585(2) 8.6.2 Gap distribution and wear depth (1) Tube wear The following formula gives the relation between tube wear volume and wear depth at AVB contact point. The relation curve is described in Fig.8.6.2-1.

V =IR 2(0 -sin 0) -L 2

h

= cos' 1- hx2 V: Wear volume R: Tube radius h: Wear depth L: Wear width 0: Wear angle On the other hands, the relation between tube wear volume and wear depth at TSP contact point is expressed as below equation obtained by 3 dimensional model (See Appendix-10 of Reference 2 for detail) and shown in Fig.8.6.2-2.

Fig.8.6.2-1 Tube wear curve at AVB contact point Fig.8.6.2-2 Tube wear curve at TSP contact point MITSUBISHI HEAVY INDUSTRIES, LTD.

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In this study, tube wear percentage after 22+6 months operation in Unit-2 is predicted according to the following steps with above two curves.

1) Wear percentage after 22 months operation (ECT result) is converted to wear volume.

2) Wear rate is calculated by dividing wear volume by 22 months at each tube contact point.

3) Wear volume after 22+6 months operation is predicted by multiplying wear rate by 22+6 months.

4) Wear percentage after 22+6 months operation is converted from 3) wear volume by using above two wear curves.

The cumulative probabilities of wear percentages at each Category after 22+6 months operation are summarized in Fig.8.6.2-3.

(2) AVB wear AVB itself is being worn according to tube wear progress. In this study, the condition that AVB wear progresses is taken into account conservatively, because more severe AVB wear makes larger gap between a tube and an AVB.

The ratio of wear coefficient between AVB ( ) and tube (TT690) is estimated to be ( ) based on MHI test results (Reference 21). The test results showed the wear coefficient ratio between ( 3 I ) is ( )to ( .)Consequently, the wear coefficient ratio ( 3 is conservatively regarded as ( )for this study, which means that AVB wear volume is half of Tube wear volume. In this study, the relation of AVB wear depth with tube wear depth is calculated as follows:

1) To calculate a section of tube wear surface in each tube wear percentage

2) To calculate AVB wear volume by using the ratio of wear coefficient from tube wear volume in each tube wear percentage

3) To calculate AVB wear depth by dividing 2) by 1) in each tube wear percentage The result of above calculation is shown in Fig.8.6.2-4. Formula of the relation is approximately expressed as ). Therefore, AVB wear depth is regarded as ( ] of tube wear depth in this study.

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Document No. L5-04GA585(2)

AVB points TSP points

-~11 Categoryl: Plugged tubes which have tube-to-tube wear (TTW) indications A AVB points TSP points Category2: Plugged tubes which have AVB wear indications A AVB points TSP points Category3: Unplugged tubes which have AVB wear indications in the center columns (Col.48-130)

AVB points TSP points Ak Category4: Unplugged tubes which have AVB wear indications in the peripheral columns (Col.1-47 and 131-177)

Fig.8.6.2-3 the cumulative probabilities of wear percentages after 22+6 months operation A MITSUBISHI HEAVY INDUSTRIES, LTD.

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Fig.8.6.2-4 the relation of wear depth between AVB and tube MITSUBISHI HEAVY INDUSTRIES, LTD.

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Document No. L5-04GA585(2) 8.7. Analysis results The tube-to-AVB contact forces at all intersections between tubes and AVBs are obtained and the results are included in the electronic files shown in Table 8.7-1, which are attached with this report.

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Table 8.7-1 Output Files of Analysis Results Case Output File Name 5-9-259 OUTPUTSONGSQUARTERMODEL01_CASE5-9-259_RANDGAPSTATIC01.dat.csv 5-9-261 OUTPUT SONGS QUARTER MODEL01 CASE5-9-261 RAND GAP STATIC01.dat.csv 5-9-262 OUTPUT SONGS QUARTER MODEL01 CASE5-9-262 RAND GAP STATICOl .dat.csv 5-9-263 OUTPUTSONGS_QUARTERMODEL01_CASE5-9-263_RANDGAPSTATIC01.dat.csv 5-9-264 OUTPUT SONGS QUARTER MODEL01 CASE5-9-264 RAND GAP STATICO0.dat.csv 5-9-265 OUTPUT SONGS QUARTER MODEL01 CASE5-9-265 RAND GAP STATIC01 .dat.csv 5-9-266 OUTPUT SONGS QUARTER MODEL01 CASE5-9-266 RAND GAP STATICOl .dat.csv 5-9-267 OUTPUTSONGSQUARTERMODEL01_CASE5-9-267_RANDGAPSTATIC01.dat.csv 5-9-268 OUTPUT SONGS QUARTER MODEL01 CASE5-9-268 RAND GAP STATICOl .dat.csv 5-9-269 OUTPUT SONGS QUARTER MODEL01 CASE5-9-269 RAND GAP STATIC01 .dat.csv 5-9-270 OUTPUTSONGSQUARTERMODEL01_CASE5-9-270_RANDGAPSTATICO1.dat.csv 5-9-271 OUTPUT SONGS QUARTER MODEL01 CASE5-9-271 RAND GAP STATICOl .dat.csv 5-9-272 OUTPUTSONGSQUARTERMODEL01_CASE5-9-272_RAND_GAPSTATICOl .dat.csv 5-9-273 OUTPUTSONGSQUARTERMODEL01_CASE5-9-273_RANDGAPSTATICOl .dat.csv 5-9-274 OUTPUTSONGS_QUARTERMODEL01_CASE5-9-274_RAND_GAPSTATIC01 .dat.csv 5-9-275 OUTPUT SONGS QUARTER MODEL01 CASE5-9-275 RAND GAP STATICOl .dat.csv 5-9-276 OUTPUT SONGS QUARTER MODEL01 CASE5-9-276 RAND GAP STATICOl .dat.csv 5-9-297 OUTPUT SONGS QUARTER MODEL01 CASE5-9-297 RAND GAP STATICOl .dat.csv 5-9-298 OUTPUT SONGS QUARTER MODEL01 CASE5-9-298 RAND GAP STATICO0 .dat.csv 5-9-299 OUTPUT SONGS QUARTER MODEL01 CASE5-9-299 RANDGAP STATICO1.dat.csv 5-9-300 OUTPUT SONGS QUARTER MODEL01 CASE5-9-300 RAND GAP STATIC01 .dat.csv 5-9-306 OUTPUT SONGS QUARTER MODEL01 CASE5-9-306 RAND GAP STATIC01.dat.csv 5-9-307 OUTPUTSONGSQUARTERMODEL01_CASE5-9-307_RANDGAP STATIC01.dat.csv 5-9-308 OUTPUTSONGS_QUARTERMODEL01_CASE5-9-308 RANDGAPSTATICO1.dat.csv 5-9-309 OUTPUT SONGS QUARTER MODEL01 CASE5-9-309 RAND GAP STATICOl .dat.csv 5-9-311 OUTPUT SONGS QUARTER MODEL01 CASE5-9-311 RAND GAP STATICO1.dat.csv 5-9-312 OUTPUT SONGS QUARTER MODEL01 CASE5-9-312 RAND GAP STATICO1.dat.csv 5-9-313 OUTPUTSONGSQUARTERMODEL01_CASE5-9-313_RANDGAP STATICO1.dat.csv 5-9-314 OUTPUT SONGS QUARTER MODEL01_CASE5-9-314_RANDGAPSTATICO1.dat.csv 5-9-315 OUTPUT SONGS QUARTER MODEL01 CASE5-9-315 RAND GAP STATICO1.dat.csv 5-9-316 OUTPUT SONGS QUARTER MODEL01 CASE5-9-316 RAND GAP STATIC01.dat.csv 5-9-317 OUTPUT SONGS QUARTER MODEL01 CASE5-9-317 RAND GAP STATIC01.dat.csv 5-9-318 OUTPUT SONGS QUARTER MODEL01 CASE5-9-318 RAND GAP STATICO1.dat.csv 5-9-319 OUTPUT SONGS QUARTER MODEL01 CASE5-9-319 RAND GAP STATICO1.dat.csv MITSUBISHI HEAVY INDUSTRIES, LTD.

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9. Reference (1) L5-04GA567 the latest revision, Evaluation of Stability Ratio for Return to Service (2) L5-04GA564 the latest revision, Tube Wear of Unit-3 RSG - Technical Evaluation Report (3) L5-04FU001 the latest revision, Component and Outline Drawing 1/3 (4) L5-04FU002 the latest revision, Component and Outline Drawing 2/3 (5) L5-04FU003 the latest revision, Component and Outline Drawing 3/3 (6) L5-04FU021 the latest revision, Tube Sheet and Extension Ring 1/3 (7) L5-04FU022 the latest revision, Tube Sheet and Extension Ring 2/3 (8) L5-04FU023 the latest revision, Tube Sheet and Extension Ring 3/3 (9) L5-04FU051 the latest revision, Tube Bundle 1/3 (10) L5-04FU052 the latest revision, Tube Bundle 2/3 (11) L5-04FU053 the latest revision, Tube Bundle 3/3 (12) L5-04FU1 lithe latest revision, AVB assembly 1/9 (13) L5-04FU1 12 the latest revision, AVB assembly 2/9 (14) L5-04FU1 13 the latest revision, AVB assembly 3/9 (15) L5-04FU1 14 the latest revision, AVB assembly 4/9 (16) L5-04FU1 15 the latest revision, AVB assembly 5/9 (17) L5-04FU1 16 the latest revision, AVB assembly 6/9 (18) L5-04FU 117 the latest revision, AVB assembly 7/9 (19) L5-04FU1 18 the latest revision, AVB assembly 8/9 (20) L5-04FU1 19 the latest revision, AVB assembly 9/9 (21) WNSY1568 Test results of wear coefficient between TT690 and 405ss JA (22) SONGS document 1814-AU651-M0146 (AREVA doc 51-9187230),Operational Assessment, MITSUBISHI HEAVY INDUSTRIES, LTD.

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Attachment-I Case study of Representative Tubes for Evaluation of Force to Prevent In-Plane FEI

1. Purpose The purpose of this attachment is to evaluate the sensitivity of the forces to prevent the in-plane FEI of additional tubes (R81 C89 and R1 31 C89) specified by AREVA.

2. Thermal and Hydraulic flow of steam generator secondary side The ATHOS thermal hydraulic analysis program was used to determine the distributions of fluid gap velocity in the normal direction to tube in-plane and fluid density. Fig A-1 and Fig.A-2 show the flow characteristics of R81 C89 and R131 C89 at 70% and 100% thermal power condition.

MITSUBISHI HEAVY INDUSTRIES, LTD.

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K 2j (a) Flow Velocity (b) Flow density Row81 Col89 (a) Flow Velocity (b) Flow density Row131 Col89 Fig. A-1 Flow Characteristics of R81 C89 and R1 31 C89 at 70% Thermal Power MITSUBISHI HEAVY INDUSTRIES, LTD. D Page 66 of 85 S023-617-1-M 1543, REV. 0

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-I (a) Flow Velocity (b) Flow density Row8l Col89 1f

-1)

(a) Flow Velocity (b) Flow density Row131 Col89 Fig. A-2 Flow Characteristics of R81 C89 and R131 C89 at 100% Thermal Power MITSUBISHI HEAVY INDUSTRIES, LTD. J Page 67 of 85 S023-617-1-Mi 1543, REV. 0

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3. Results The difference of contact force between the representative tubes and additional tubes is not significant in both of 70% and 100% thermal power as shown in the following tables.

Table A-1 Summary of Results for 70% Thermal Power Unit: N Category Representative B01 B02 B03 804 B05 B06 807 808 B09 B10 B1l B12 tubes 1 R113 C81 r "_

2 R97 C89 3 R98 C90 Additional R81 C89 Additional R131 C89 _

Table A-2 Summary of Results for 100% Thermal Power Unit: N Category Representative B01 B02 B03 B04 B05 B06 B07 B08 B09 B10 311 B12 tubes 1 R113 C81 r(

2 R97 C89 3 R98 C90 Additional R81 C89 Additional R131 C89 EE MITSUBISHI HEAVY INDUSTRIES, LTD.

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Attachment-2 Case study of Methodology to Calculate Force to Prevent In-Plane FEI

1. Evaluation Cases The contact forces required to activate AVB supports can be reduced by changing the evaluation method. Following 2 cases are performed to calculate the contact forces of Row 97 Column 89 (Representative tube of Category 2) at 70% power and 100% power.

Case A (Original case)

The reaction force of in-plane Fj and out-of-plane Fo are calculated as the maximum independently.

F,= max+ }.(ty F0 = max {F (t)}

The contact force Fc, which is sufficient to prevent slip motion by friction force is calculated as follows.

Where,

/u : Friction coefficient By taking into account of contact force reduced by the reaction force Fo in the out-of-plane direction, the required contact force, Freq, is derived by the equation below.

Freq=Fý+Fo Case B (2 a)

By taking into account of the variability of the turbulent excitation force, 2 a of the reaction forces of in-plane Fj and out-of-plane F, are calculated by the following equations.

2 Fj = ,fF0 (t) + [ý(t)2 F0 =FQ) p N F, = 2a MITSUBISHI HEAVY INDUSTRIES, LTD.

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2. Results The contact forces of Row 97 Column 89 (Representative tube of Category 2) at 70% power and 100%

power are calculated and compared with the original case (Case A) as shown in Table 1-1 and 1-2.

Table 1-1 Contact Force Re uired to Activate AVB Supports at 70% Thermal Power Case A

B Cate 0goy 2

2 Representative tubes R97C89 R97 C89 B01 2__

B 02 B 03 B 04 B 05 B 06 B 07 B 08 B 09 BIO B 11 B 12 Table 1-2 Contact Force Required to Activate AVB Supports at 100% Thermal Power Case Cate Representative BO1 B 02 B 03 B 04 B 05 B 06 B 07 B 08 B 09 B 10 B11 B 12 gory tubes A 2 R97C89 - 4 B 2 R97 C89 MITSUBISHI HEAVY INDUSTRIES, LTD.

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Attachment-3 Influence of a tube at Stay Rod address on Contact forces in the Full Bundle

1. Purpose There is a tube at the each stay rod address in the full bundle analysis model, although no tube at stay rod address in real full bundle. The stay rod address is shown in Tab. 1-1. This attachment provides how much influence the tubes at stay rod addresses have on contact forces between AVBs and tubes in the full bundle.

Tab.1 -1 Stay Rod Address (for the quarter model)

Row Column Row Column Row Column 2 40 25 75 57 57 2 66 31 45 66 66 14 68 32 84 72 74 15 41 44 50 76 84

2. Conclusions Eliminating the tubes at stay rod address decreases contact forces on the adjacent tubes in adjacent column, and increases contact forces on the adjacent tubes in the same column. However, the range of the influence reaches only several tubes, not so large. The cumulative probability of the contact force is almost same between eliminating case and the original case. It can be considered that the full bundle model with a tube at each stay rod address is valid for calculation of the in-plane FEI occurrence probability.

3. Acceptance Criteria There is no criterion, because this study is just to confirm influence of tube at stay rod address on contact forces between AVBs and tubes.

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4. Analysis Case 2 cases are additionally performed in this study. Case 5-2-1 and Case 6-2-1 model a tube at each stay rod address as original case. Case 5-2-5 and Case 6-2-4 model no tube at the stay rod address. Case 5-2-1 and Case 5-2-5 simulate Unit-2 A-SG at Cycle 17th. Case 6-2-1 and Case 6-2-4 simulate Unit-3 A-SG at Cycle 17th.

Tab.4-1 Analysis cases I Unit Stay rod address Case 5-2-1 Unit 2 A-SG There are tubes at stay rod addresses.

Case 5-2-5 Unit 2 A-SG There is no tube at stay rod address.

Case 6-2-1 Unit 3 A-SG There are tubes at stay rod addresses.

Case 6-2-4 Unit 3 A-SG There is no tube at stay rod address.

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5. Analysis Results Fig.5-1 shows change of the contact forces between tubes at the same row in Case 5-2-1 and Case 5-2-5. The figures indicate that the contact forces on the adjacent tubes in adjacent column in Case 5-2-5 (with no tube at stay rod address) decrease more than the original case. This is caused by that the 2 AVBs at stay rod address come close due to manufacturing dispersion. Fig. 5-2 shows change of the contact forces between tubes in the same column in Case 5-2-1 and Case 5-2-5. In this comparison, the contact forces in Case 5-2-5 (with no tube at stay rod address) increase more than the original case, since the 2 AVBs at stay rod address come close to each other and the 2 AVBs hold more tightly the adjacent tube in the same column. Same trend of the contact force is confirmed in Fig.5-3 and Fig.5-4 for Unit-3 case. Fig.5-5 and Fig.5-6 give the cumulative probabilities of the contact forces in Category 2+3 in Case 5-2-1 V.S. Case 5-2-5 for Unit 2 A-SG and Case 6-2-1 V.S. Case 6-2-4 for Unit 3 A-SG.

The cumulative probabilities are almost same as each other case. Therefore, the full bundle model with a tube at each stay rod address is valid for calculation of the in-plane FEI occurrence probability.

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Case5-2-1 (Original Case: with a tube at each stay rod address)

Case5-2-5 (with no tube at stay rod address)

Fig.5-1 Contact forces distribution at Row 76 in Unit 2 (Case 5-2-1 and 5-2-5)

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Document No. L5-04GA585(2) rA Case5-2-1 (Original Case: with a tube at each stay rod address)

Case5-2-5 (with no tube at stay rod address)

Fig.5-2 Contact forces distribution in Column 84 in Unit 2 (Case 5-2-1 and 5-2-5)

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Document No. L5-04GA585(2) r A.

K Case6-2-1 (Original Case: with a tube at each stay rod address) r K -I Case6-2-4 (with no tube at stay rod address)

Fig.5-3 Contact forces distribution at Row 76 in Unit 3 (Case 6-2-1 and 6-2-4 MITSUBISHI HEAVY INDUSTRIES, LTD.

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Case6-2-1 (Original Case: with a tube at each stay rod address)

Case6-2-4 (with no tube at stay rod address)

Fig.5-4 Contact forces distribution in Column 84 in Unit 3 (Case 6-2-1 and 6-2-4)

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(a) Case5-2-1 (Original Case: with a tube at each stay rod address)

K -7 (b) Case5-2-5 (with no tube at stay rod address)

Fig.5-5 Cumulative probabilities of contact force (Category2+3) in Unit 2 (Case 5-2-1 and 5-2-5)

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J (a) Case6-2-1 (Original Case: with a tube at each stay rod address)

(b) Case6-2-4 (with no tube at stay rod address)

Fig.5-6 Cumulative probabilities of contact force (Category2+3) in Unit 3 (Case 6-2-1 and 6-2-4)

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Attachment-4 Verification of the Quarter Full Bundle Model

1. Purpose The purpose of this attachment is to verify the quarter full bundle model by comparing the cumulative probabilities of contact forces between the quarter full bundle model and the half full bundle model.

2. Conclusions The quarter full bundle model is verified because it is confirmed that the results of the quarter model are consistent with the half full bundle model results.

3. Acceptance Criteria The contact forces in the quarter model are to correspond with the half full bundle model.

4. Assumption The model area is a quarter by taking into account symmetry, so that the inputted manufacturing dispersion in Hot side is symmetry same as Cold side.

5. Methodology In order to verify the quarter full bundle model, the following steps are conducted;

1) to input random manufacturing dispersion to the half full bundle model

2) to input the manufacturing dispersion distributed in Hot side of the half full bundle model to the quarter full bundle model

3) to compare of cumulative probability of the contact forces in the quarter full bundle model with the full bundles MITSUBISHI HEAVY INDUSTRIES, LTD.

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-A-

6. Verification Results 6.1 Analysis model All parts of the U-bend assembly above the #6 TSP (Tubes, AVBs, Retaining bars, Retainer bars and Bridges) are modeled as beam elements. Figure 6.1-1 shows overview of the quarter full bundle model.

The model area is a quarter by taking into account symmetry. The contact points between tube to AVB, and tube to TSP are modeled as gap elements, which show spring property in compression.

L L.

Bird's-eye View of the Model Front View of the Model Fig.6.1-1 Analysis model 6.2 Analysis cases for verification The analysis cases for verification are shown in Tab.6.2-1. Random manufacturing dispersions are different between at BOL and after additional 6 months operation.

Tab.6.2-1 Analy is cases for verification The quarter model The half model Unit-2A at BOL Case 4-1-106 Case 4-1-98 Unit-2A after additional 6 months operation Case 4-1-107 Case 4-1-72 MITSUBISHI HEAVY INDUSTRIES, LTD.

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Document No. L5-04GA585(2) 6.3 Comparison of cumulative probability of the contact forces Fig.6.3-1, Fig.6.3-2, Fig.6.3-3, and Fig.6.3-4 show cumulative probabilities of the contact forces on tubes of the quarter model and the half model. The red lines for the quarter good correspond with the blue lines for the half model at from B01 to B05. The probability of lower level contact forces at B6 in the quarter are increased a few more than the half results, because relative displacement between B6 and B7 on a tube is not generated in the quarter model due to symmetry condition, so that there is little off-set loading at 86. However, these differences are judge to be negligible small. Therefore, the quarter full bundle model is valid for the calculation of in-plane FEI occurrence.

r 1ý11sý'

Fig.6.3-1 Cumulative probabilities of the contact forces in Category2 of U2A at BOL A MITSUBISHI HEAVY INDUSTRIES, LTD.

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CA Fig.6.3-2 Cumulative probabilities of the contact forces in Category3 of U2A at BOL /

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JA Fig.6.3-3 Cumulative probabilities of the contact forces in Category2 of U2A after additional 6 months MITSUBISHI HEAVY INDUSTRIES, LTD.

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A Fig.6.3-4 Cumulative probabilities of the contact forces in Category3 of U2A after additional 6 months MITSUBISHI HEAVY INDUSTRIES, LTD.

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