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FLORIDA POWER AND LIGHT COMPANYNUCLEAR ENGINEERING DEPARTMENT

P.O. Box 14000Juno Beach, Florida 33408

St. Lucie Nuclear Power Plant

Unit 2

ATTACHMENT8

STRESSES FORST. LUG I E UNIT 2

PRESSURIZER LEFM

Prepared by

BBW NUCLEAR SERVICE COMPANY

For

St. Lucie Nuclear Power Plant10 Miles South of Ft. Pierce on A1A

Ft. Pierce, Florida 33034

Commercial Service Date:

NRC Docket Number.

Document Number.

Revision Number. 0

August 8, 1983

50-389

32-1235127-01

Date: February 15, 1995

FHQ: PSL1SNB.RPT Page 3

95030703&i 950302PDR ADOCK 050003B9P PDR

BWNT-20697-2(11/89)

JllBBMINUCLFAHCMTECHNOI.OGIES

CALCULATlONALSUMMARYSHEET (CSS)

DOCUMENT IDENTIFIER 32-1235127-01

TITLE Stresses for St. Lucie Unit 2, Pressurizer LEFM

PREPARED BY'EVIEWEDBY:

A.M. MIller

SIGNATUR

TITLE Engr. IV

COST 41020 REF.

~AME H.T. Harriso

SIGNATUR

~~ 9'5 TITLE Princi al En r.

38 TM STATEMENT'EVIEWER

PURPOSE AND SUMMARYOF RESULTS

The purpose of this document was to determine enveloping Normal and Upset, Condition stresses

for the seven 1" instrumentation/temperature sensing nozzles in the pressurizer at St. Lucie

Unit 2. Results from this document were used as inputs to the fracture mechanics evaluation,Reference [7].

e stress results are summarized in Tables 6-1 through 6.8 in Section 6.0. Note that thermalstratification effects were not considered in this analysis.

**BWNT NON-PROPRIETARY**

THE FOLLOWINGCOMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT:

CODE IVERSION IREV CODE IVERSION IREV THIS DOCUMENTCONTAINS

ASSUMPTIONS THATMUST BE

VERIRED PRIOR TO USE

ON SAFETY-RELATEDWORK

YES( ) No( X )

FAG ~ OF

BGW NUCLEAR TECHNOLOGIES **BWNT NON-PROPRIETARY** 32-1235127-01

RECORD OF REVISIONS

RevisionNumber

PagesAdded/

Chanched Descri tion

All Original issue

01 All Issue of Non-Proprietary Version

Prepared By: A.M. MillerReviewed By: H.T. Harrison

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BRW NUCLEAR TECHNOLOGIES **BWNT NON-PROPRIETARY** 32-1235127-01

1.0 Introduction 4

2. 0 Assumptions 4

3.0 Design Inputs3.1 Design Characteristics3.2 Material Properties3.3 Model Geometry

~ ~ ~ ~ 5

~ ~ 0 ~ 6

8

4.0 Finite Element Model . . . . . . . . . . . . . . . . . . . . . . . 10

5.0 Thermal Analysis . . . . . . . . . . . . . . . . . . . ~ . . . . . 10

6.0 Stress Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . 18

7.0 ANSYS 5.0A Verification . . . . . . . . . . . . . . . . . . . . . . 37

8.0 References 38

9.0 Microfiche ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 39


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1.0 Introduction

During the 1994 refueling outage, external leakage was identified at thepressurizer instrument nozzle "C" of Florida Power & Light Company's St. LucieUnit 2. Subsecpxent NDE identified indications on the J-welds for all four steam

space instrument nozzles. Modifications were made and justifications performedto determine the potential for crack growth during plant operation. The

evaluation performed at the time was conservatively limited to one cycle based

on the design information available. The purpose of this analysis is to providestress analysis input for a bounding fracture mechanics flaw evaluation so thatit is applicable to all seven instrument/temperature 1" nozzles in thepressurizer.

Results from this document were used as inputs to the fracture mechanics

evaluation, Reference [7]. The results were presented in the coordinate systemof the postulated flaw as recpxired by Reference [7] since the fracture mechanicsevaluation determined the postulated flaws, see Figure 6.2. The component

stresses along a postulated flaw plane shown in Figure 6.2 were determined usingANSYS 5.0A finite element software.

2.0 Assumptions

1) Material properties for SA-240, Type 304 were assumed for the stainlesssteel cladding on the pressurizer heads and shell.

2) The effects of the nozzle were neglected in determining the shell/headstresses (i.e. the nozzle was omitted from the finite element model) .

3) The hT between the cladding surface temperature and the bulk fluidtemperature was assumed to be a specific hT'F for calculating the naturalconvection heat transfer coefficient.

4) Piping loads on the instrumentation/temperature sensing nozzles producenegligible stresses on the pressurizer shell/head.

5) Effects of thermal stratification were not considered in this analysis.

6) Hydrotest was assumed to be shop hydrotest only. Therefore, no futurehydrotests are assumed to occur.


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3.0 Design Inputs

3.1 Design Characteristics

The following design parameters for the pressurizer were taken from Reference

[8] .

HeatupCooldownOperating PressureOperating TemperatureMinimum Pressure (Reactor Triptransient)Maximum Pressure (Abnormal Lossof Load transient.)

100'F/hr200'F/hr2250 psia653 F

1740 psia (653-616 'F hT)

2400 psia (664-614 'F hT)


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3.2 Material Properties

This section summarizes the material properties used in the thermal/stressanalysis. The material types come from References [8-10] and assumption 1.References for the material properties are given in the tables below. The

material property designation and units are:

KXX - thermal conductivity, btu/(hr-in-'F)DENS - density, lb/in'

- specific heat, btu/(lb-'F)C is a calculated value based on C KXX/(DENS x Thermal Diffusivity)where thermal diffusivity is taken from the same source as KXX

EX - Young's Modulus, psi x10'LPX- coefficient of thermal expansion, in/in/'F x 10~

Sm - design stress intensity, ksiSy - yield strength, ksiSu - ultimate strength, ksiv - Poisson's ratio ~ .3 for all materials

PRESSURIZER HEADS AND SHELLSA-533 GR-B CL-1, Low Alloy Steel

(Mn-.SMo-.SNi)

TEMP

100

200

300

400

500

600

700

REF

DENS

.2839

. 2831

.2823

.2817

.2809

.2802

.2794

1.8833

1. 9500

1. 9833

1.9833

1. 9583

1. 9167

1. 8583

. 1079

.1139

. 1196

.1257

.1323

.1389

. 1448

EX

29.3

28.8

28.3

27.7

27.3

26.7

25. 5

ALPX

7.06

7.25

7.43

7.58

7.70

7 '37. 94

Sm

26.7

26.7

26.7

26.7

26.7

26.7

26.7

Sy

50.0

47.5

46. 1

45.1

44.5

43.8

43.1

Su

80.0

80.0

80.0

80.0

80.0

80.0

80.0


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B&W NUCLEAR TECHNOLOGIES **BWNT NON"PROPRIETARY** 32-1235127-01

HEAD AND SHELL CLADDING304 STAINLESS STEEL, SA-240 ASSUMED

(18Cr-8Ni)

TEMP

100

200

DENS

.2862

.2853

.7250

.7750

. 1157

. 1209

EX

28. 1

27.6

ALPX

8.55

8.79

20.0

Sy

30. 0

20.0 '25.0

Su

75.0

71.0

300

400

500

600

700

REF

.2844

.2836

.2827

.2818

.2810

.8167

.8667

.9083

. 9417

.9833

. 1246

. 1286

. 1313

.1334

. 1358

27.0

26.5

25.8

25.3

24.8

9.00

9. 19

9.37

9.53

9.69

20.0

18.7

17. 5

16.4

16. 0

22.5

20.7

19.4

18.2

17.7

66.0

64.4

63.5

63.5

63.5


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BGW NUCLEAR TECHNOLOGIES **BWNT NON-PROPRIETARY** 32-1235127-01

3.3 Model Geometry

To bound all instrument/temperature sensing nozzle locations in the pressurizerheads and shell, the radius of the modeled nozzle penetration was determined so

that the total pressure stress would ecpxal or exceed the total pressure stresspresent at all nozzle locations. Penetrations in the spherical heads experienceincreased stress due to the hillside effect of the skewed penetration.Penetrations in the cylindrical portion of the shell experience increased stressdue to the larger hoop stress and the larger stress concentration effects due tothe stress profile around the penetration.

The model inherently included stress to account for the hillside effect and thestress for the stress concentration effect at a hole in the cylindrical shell.


Date: 2 95

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BGW NUCLEAR TECHNOLOGIES **BWNT NON"PROPRIETARY** 32-1235127-01

IJJCL0-I-C)

(UI

CC

CC

I-DCC

Figure 3.1, Finite Element Model Geometry and Materials (inches)


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B&W NUCLEAR TECHNOLOGIES **BWNT NON-PROPRIETARY** 32-1235127-01

4.0 Finite Element Model

ANSYS 5.0A finite element software, Reference [6], was used to perform theaxisymmetric thermal and stress analysis of the nozzle penetration. A sufficientportion of the head/shell was modeled to attenuate the stress concentrationeffects at nozzle penetration. The head/shell and cladding were modeled usingaxisymmetric elements (PLANE 42 structural and PLANE 55 thermal).

5.0 Thermal Analysis

The transients in Ref. [8] were reviewed for those likely to produce maximum

tensile stress on the inside surface of the pressurizer (conservative for thefracture mechanics analysis in Reference [7]). Based on the review, thefollowing transients were evaluated in this analysis: 100'F/hr Heatup, 200'F/hrCooldown, a bounding Upset Condition transient which was represented as a 53'F

Step-down (pressure 1740 psia) and a 53'F Step-up (pressure 2400 psia),and'oss

of Secondary Pressure. The Heatup, Step-down, Step-up and Cooldown

transients were combined into one computer run (microfiche THERMAL.OUT) withHeatup from 70'F to 653'F (0 hours to 5.83 hours), 53'F Step-down (7 hrinstantaneous), 53'F Step-up (8 hr instantaneous) and Cooldown from 653'F to 70'F

(9 hours to 11.915 hours). The Loss of Secondary Pressure transient was run and

the results are contained in microfiche LPTHERM.OUT.

Thermal conditions were imposed on the finite element model as applied heattransfer coefficients and bulk fluid temperatures. Heat transfer was assumed tooccur at only the inside surface of the pressurizer as shown in Figure 5.1. Allother surfaces were assumed to be insulated.

A constant heat transfer coefficient was used to simplify the analysis in a

conservative manner. Since overestimating the tensile stresses at the insidesurface of the pressurizer was conservative for the fracture mechanics analysisin Reference [7], the heat transfer coefficient was selected to result inconservatively high tensile stresses on the inside surface of the pressurizer.

During Heatup and the Step-up transients, heating of the inside surface causescompression on the inside surface of the pressurizer. Therefore, use of a lowheat transfer coefficient results in conservative (tensile) stresses.Conversely, during Cooldown and the Step-down transient, a high heat transfercoefficient results in conservative (tensile) stresses. Therefore, nozzles in


Date:~2 99

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B6cW NUCLEAR TECHNOLOGIES **BWNT NON-PROPRIETARY** 32-1235127-01

the steam space were conservatively represented using heat transfer coefficientsin the water space (i.e. for heating, condensing steam coefficients are greaterthan natural convection coefficients in the water space and for cooling, naturalconvection steam coefficients are less than natural convection coefficients inthe water space).

The heat transfer correlations in Ref. [2] were reviewed for horizontal and

vertical plates. The correlation for a horizontal heating plate, face up (T„ >

Tm) was selected as a representative heat transfer coefficient for the nozzles

in the water space.

The results of the thermal analyses were reviewed using the ANSYS POST26 postprocessor to determine times when the radial hT's occurred. The temperature atthe inside surface of the pressurizer (essentially the bulk fluid temperature)

and the radial hT are shown in Figures 5.2 through 5.5. The temperaturedistribution at times of extreme hT's were then used as inputs for the stressanalyses since the extreme hT's resulted in extreme thermal stresses. Steady

state temperature cases were also run at 653 F and 2250 psia without materialdiscontinuity effects (T~„ T~„ microfiche STEADYST.OUT) and at 653'F and 2400

psia with material discontinuity effects (T , 70'F, microfiche STRESS.OUT) .

The following table summarizes the critical transient times and identifies theassociated pressures. The location of node pair used for evaluation of the hT's

was the same node pair used for the stress path in Section 6.0 and is shown inFigure 6.2 and the POST26 results are contained at the end of the thermal runs


Date: 2 95

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in the microfiche in Section 9.0. Note that although the node pair used forevaluating the radial hT was at a specified flaw angle through the shell wall,it was representative of the radial gradient since the heat transfer is one

dimensional in the radial direction (i.e., the entire inside surface isisothermal and the entire outside surface is isothermal).

TABLE 5.1, CRITICAL TRANSIENT TIMES

TRANSIENT TRANSIENT TIME (HR) PRESSURE (PSIA)

Heatup 5.83 2, 250

Step-down 7.0667 1, 740

Step-up 8.0667 2,400

Steady State'.000 2,400

Cooldown 9.5247 1,

028'ooldown

11.915

Steady State',250Loss of SecondaryPressure

.051958 200

'The pressure was assumed to equal the saturation pressure at 548'F'Includes material discontinuity temperature effects (T„, = 70'F).'Excludes material discontinuity temperature effects (T , = T„„~~ 653'F).


Date:~295Page: 12

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B6W NUCLEAR TECHNOLOGIES **BWNT NON-PROPRIETARY** 32-1235127-01

zLUDOKQ

nu?nu)0v- ~ OOCiElf Ill/)-U U.U UjNOX>.NO

oKHI-

A1VA

I IV)(91UjO0I-

Figure 5.2, Shell Radial hT Time History, Heatup, 53hT Steps 6 Cooldown


Date: 2 95

Date: 2 95 Page: 14

H

08

ANSYS 5.0 AOCT 25 199410:02:30PLOT NO. 2POST26

ZV 1DIST 0.75XF 0.5YF 0.5ZF -0.5CENTROID HIDDEN

n

i50

00I

0

M

TEMP

RAD

00000 STLUCIE1.IGS

10

TIME

12 1618

20M

I

hl4JVl

h)

IO

6l8lr. e

6l Ql

0 0td W

'C 'C

zV

0

Ul

*

0

0

n00

<C

STLUCIE1.IGS

Oo2

0.40.6

0.8

TIME

i+2 l.6

RAD

(» loca-l)

ANSYS 5.0 AOCT 25 199409:07:48PLOT NO.POST26

ZV 1DIST 0.75XF 0.5YF 0.5ZF 05CENTROID HIDDEN

n

n

0El

OgI

0

HW

4)MI

h>OJUl

W

IO


CII

Q~g)O~gg<zol0-Sl-op V)

zLUDDXO

~u)u)n<r OOOO>~i s a~+

~4I

OX

CO

~4

blKH

00

0

O

O

NO

A 1VA

(D(9

ujODe~

Figure 5.5, Inside Surface Temp and Radial hT, Loss of Secondary Pressure


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B6cW NUCLEAR TECHNOLOGIES **BWNT NON-PROPRIETARY** 32-1235127-01

6.0 Stress Analysis

The temperature distributions and pressures at the critical times in Table 5.1were imposed on the model to obtain the stresses in the pressurizer shell. The

pressure boundary conditions are shown in Figure 6.1. Since the fracturemechanics evaluation in Reference [7] requires stresses along a specified flawplane, the ANSYS POST1 post processor was used to transform the stresses into theflaw plane coordinate system as shown in Figure 6.2.

Symmetry boundary conditions were used at the edge of the pressurizer head torestrict the heads motion to only the radial direction. A nodal force was

applied to the head to represent the end cap load developed at the nozzle (nozzleend cap load = mr'(pressure) ~ w(.6875)'(pressure) ~ 1.4849(pressure)). The nodalforce was conservatively applied to the outside surface of the model since itwould tend to increase the tensile stresses in the pressurizer shell which is theregion of interest.

Complete stress results are contained in the microfiche of Section 9.0. The

stresses as required for the FM analysis are summarized in the Tables 6.1 through6.8 and Figures 6.3 through 6.10. Note that the stresses are in psi.


Date: 2 95

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BOW NUCLEAR TECHNOLOGIES NON-PROPRIETARY** 32-1235127-01

TABLE 6 ~ 1 g END OF HEATUP g P~2250 PSI

S0.00000E+000. 119590.239180.358760.478350.597940. 717530.837110.95670

1.07631. 19591.31551.43511. 55461.67421. 79381.91342.03302.15262.27222. 39182. 51132.63092.75052. 87012.98973. 10933.22893.34853.46803.58763.70723.82683.94644.06604.18564.30524.42474.54434.66394.78354. 90315.02275. 14235.26195.38145.50105.62065.7402

SX-7283.8-2390.62348.75917.87064.78210.29242.59868.310502.11084.11488.11893.12269.12553.12834.13098.13309.13515.13713.13877.14037.14192.14323.14453.14580.14686.14793.14898.14991.15083.15141.15163.15188.15246.15305.15354.15394.15433.15473.15507.15530.15553.15577.15601.15938.16287.16624.16947.17256.

SY5973.25126. 04768.95548.96676.27778.08839. 19535.710230.10889.11363.11838.12287.12640.12991.13324.13601.13873.14133.14355.14571.14780.14960.15134.15304.15450.15594.15732.15848.15965.16109.16263.16413.16513.16610.16701 ~

16784.16865.16946.17022.17087.17152.17217.17281.16990.16681.16387.16106.15838.

SZ60276.55404.50677.46241.44495.42714.41030.40141.39242.38404.37926.37440.36991.36728.36456.36206.36064.35908.35768.35692.35604.35527.35487.35441.35400.35380.35356.35334.35323.35313 ~

35295.35291.35286.35264.35241.35234.35214.35192.35170.35150.35120.35090.35060.35031.34986.34940.34894.34848.34802.


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B&W NUCLEAR TECHNOLOGIES NON-PROPRIETARY** 32-1235127-01,

TABLE 6.2, 53F STEP DOWN, P~1740 PSI

S0.00000E+000. 119590.239180.358760.478350.597940.717530. 837110.956701.07631. 19591.31551.43511. 55461.67421. 79381. 91342.03302 ~ 15262.27222. 39182.51132.63092.75052.87012.98973. 10933.22893.34853.46803.58763.70723.82683.94644 '6604.18564.30524.42474.54434.66394.78354.90315.02275.14235.26195.38145.50105.62065.7402

SX-6913. 0-1682. 63307.96953.47957.18893.39672.710050.10402.10696.10819.10932.11024.11030.11038.11037.10989.10954.10912.10846.10794.10736.10672.10615.10555.10499.10444.10391.10346.10299.10238.10162.10088.10053.10020.9980.39950.79923. 19895.99869.69852.29835.49819.19803.310004.10214.10416.10609.10794.

SY8348.26909.25990.66441. 37527.88532.99420.09888.710328.10707.10889.11060.11203.11250.11298.11332.11313.11307.11290.11246.11214.11175.11126.11084.11038.10995.10953.10911.10872.10834.10823.10828.10831

'0819.

10807.10791.10789.10789.10790.10791.10803.10816.10828.10839.10650.10452.10263.10081.9908.0

SZ70271.62772.55758.49572.46742.43956.41368.39639.37939.36375.35178.34011.32937.32044.31191.30394.29697.29052.28434.27886.27380.26888.26458.26052.25654.25317.24988.24670.24402.24135.23884.23665.23447.23257.23071.22896.22751.22611.22472.22345.22248.22152.22057.21962.21903.21846.21791.21736.21681.


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B&W NUCLEAR TECHNOLOGZES NON-PROPRZETARY** 32-1235127-01

TABLE 6.3, 53F STEP UP, P~2400 PSZ

S0.00000E+000. 119590. 239180.358760.478350.597940.717530. 837110.95670

1.07631.19591. 31551.43511. 55461.67421.79381. 91342.03302. 15262.27222.39182.51132.63092.75052.87012.98973.10933.22893.34853.46803.58763.70723.82683.94644.06604. 18564.30524.42474.54434.66394.78354. 90315.02275. 14235. 26195. 38145.50105.62065.7402

SX-7254.5-2602.91924.95376.56556.37759. 18874.09593.910334.11027.11544.12066.12554.12950.13338.13705.14019.14316.14605.14855.15091.15324.15523.15716.15906.16065.16222.16377.16510.16643.16734.16781.16832.16912.16995.17065.17121.17175

'7229.

17276.17306.17337.17368.17400.17777.18168.18544.18905.19251.

SY5009.84374.64204.65068.26184.47297.48404 '9179.89966.410731.11319.11914.12486.12961.13433.13885.14279.14658.15025.15349.15656.15955.16217.16466.16711.16919.17123

'7319.

17481.17644.17833.18028.18220.18347.18471.18589.18691.18790.18889.18981.19056.19132.19207.19282

'8956.

18611.18281.17966.17668.

SZ55366.51513.47681.43963.42672.41314.40030.39507.38957.38443.38279.38091.37914.37923.37897.37877.37966.38007.38058.38169.38238.38318.38420.38500.38585.38668.38744.38815.38881.38946.38994.39048.39101.39119.39134.39167.39173 ~

39175.39176.39177.39158.39139.39119.39099.39055.39009.38962.38915.38867.


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TABLE 6.4, STEADY STATE, Tref 70F, Tunif 653F, P = 2400 PSIA

S0.00000E+000. 119590.239180.358760.478350.597940 ~ 717530. 837110.956701. 07631. 19591.31551.43511.55461.67421.7938l. 91342.03302.15262.27222.39182.51132.63092.75052.87012.98973.10933.22893.34853.46803.58763.70723.82683.94644.06604.18564.30524.42474.54434.66394.78354 ~

9031'.0227

5.14235.26195.38145. 50105.62065.7402

SX-8203.5-2489.23016.77124. 08389.69630.610730.11367.12002.12576.12950.13321.13659.13895.14127.14342.14499.14653.14797.14906.15014.15116.15196.15275.15351.15411.15471.15531.15582.15632.15649.15633.15620.15646.15675.15693.15708.15724.15739.15751.15759.15767 ~

15776.15785.16120.16469.16804.17126.17434.

SY7687.16501.05884.86653.77928.79155.610311.11033.11745.12410.12859.13306.13723.14028.14332.14617.14837.15055

'5260.

15424.15585.15737.15861.15983.16099.16195.16289.16379.16451.16524,16627.16743.16857.16924.16989.17048.17106.17164.17221.17276.17327.17377.17428

'7478.

17179.16864.16563.16275.16001.

SZ72516.66004.59778.54082.51714.49332.47103.45809.44517.43322.42543.41766.41049.40544.40042.39574.39228.38882.38558.38308.38058.37821.37634.37446.37266.37121.36975.36833.36717.36600.36483.36387.36292.36193.36094.36012.35931.35851.35772.35699.35631.35565.35498.35432.35372.35312.35253.35193.35134.


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B&W NUCLEAR TECHNOLOGIES NON-PROPRIETARY** 32-1235127-01

TABLE 6.5, COOLDOWN, Psat=1028 PSIA

S0.00000E+000. 119590.239180.358760.478350.597940.717530.837110.95670

1.07631. 19591. 31551.43511.55461.67421. 79381 ~ 91342.03302.15262.27222. 39182. 51132.63092.75052.87012.98973.10933.22893.34853.46803.58763.70723.82683.94644.06604. 18564.30524.42474.54434 '6394.78354.90315.02275. 14235.26195.38145. 50105.62065.7402

SX-4251. 9-949.122183.54457.55075.95642.06110.76333.86537.56703.06763 '6815.36851. 06834.56816.96791. 26737.16688.06633. 16563.86500.66433.46361. 26293.06222.36153. 76085.96019. 05957.75895.35825.55749.15673.45623.65575.35523.15481. 35441.55402.05364.65338.65313. 05287.85263.05363.85470.85573.35671.35764.8

SY5658.24628.93925.54126.64801. 85420. 15958.36232.96488.46707.96802.56889.76958.56965.96972.46968.36931.06898.16857.66799.76746.86688.86624.26562.56497.96434.86372.36309.86250.46190.66147.26114.06079.56040.66001. 65960.25932.05906. 15880.05856.35846.35835.95825.35814.45707.65596.85490.35388.15290.2

SZ45637.40460.35641.31472.29573.27713.26003.24848.23716.22680.21877.21094.20370.19760.19173.18620.18130.17668.17222.16818.16438.16067.15731.15411.15095.14816.14542,14276.14041.13807.13586.13386.13186.13011.12839.12674.12536.12403.12271.12149.12059.11969.11879.11791.11743.11699.11655.11612.11569.

PreparedReviewed

By: A.M. MillerBy: H.T. Harrison

Date: 2 95

Date: 2 95 Page: 23


TABLE 6.6, END OF COOLDOWN, P~O PSI

S0.00000E+000. 119590.239180.358760.478350.597940. 717530. 837110.95670

1. 07631.19591. 31551.43511.55461. 67421. 79381. 91342.03302. 15262.27222.39182. 51132.63092.75052. 87012.98973. 10933.22893.34853.46803.58763.70723.82683.94644.06604. 18564.30524.42474.54434.66394.78354.90315.02275. 14235.26195.38145.50105.62065.7402

SX-519. 07

129. 63701.441078. 81148. 31181. 91182. 21146. 21094 '1031. 4954.61871. 24785.65694.22602.49510.30415.58324. 91233.00141. 5754.659

-33.564-117.81-199. 13-281.30-356.35-430.77-504.36-570.83-637.84-699.27-754.44-810. 04-858.93-907.49-955.43-994. 11-1031.2-1068.3-1102. 5-1125.9-1149. 3-1172. 6-1195. 7-1229.8-1263. 7"1296. 6-1328. 4-1359.1

SY2077.71580.41144. 8988.461099.81183. 71219.91190.41150. 61098. 61021. 0938.62852 '8754.86657.42558.39454.90355.00253.68152. 2055.383

-42.486-136.32-226. 71-317. 58-400.69-482.67-563. 15-635.20-707 '0-777.36-843.39-909.32-963.51-1016.9-1070.3-1112. 6-1153. 1-1193. 7-1231 03-1256.9-1282.6-1308. 5-1334.6-1317. 7-1298. 4-1280.5-1263. 8-1248.4

SZ12153.10004.8066.56563.85865.25204.24606.34128.03668.53253.82882.42526.72198. 21888.01595. 41317. 91048. 9800. 61558 '6323 '1106. 80

-107 '4-310.33-501.66-691. 53"864.00-1032. 2-1196. 1-1343.4-1490.0-1626. 1-1752.9-1879.0-1984.9-2088.8-2193. 2-2276.2-2355.1-2433.4-2506.0-2555.8-2605. 1-2653 '-2702.2-2720.1-2735.3-2750.1-2764.5-2778.6


Date: 2 95

Page: 24

B&W NUCLEAR TECHNOLOGZES **BWNT NON-PROPRIETARY** 32-1235127-01

TABLE 6.7, STEADY STATE Tunif Tref 653, P=2250 PSI

S0.00000E+000. 119590.239180.358760.478350.597940.717530. 837110.95670

1.07631. 19591. 31551.43511.55461.67421.7938l. 91342.03302. 15262.27222.39182.51132.63092.75052. 87012.98973. 10933.22893.34853.46803.58763.70723.82683.94644.06604.18564.30524.42474.54434.66394.78354. 90315.02275.14235.26195.38145. 50105.62065.7402

SX-7698.3-2331.22839.06694.97882.49046.210077.10674.11270.11807.12157.12503.12820.13039.13255.13455.13600.13743.13877.13977.14077.14172.14245.14318.14388.14443.14498.14552.14599.14645.14660.14644.14631.14654.14681.14697.14710.14724.14738.14749.14755.14762.14770.14778.15092.15418

'5732

'6033.

16321.

SY7242 '6121.45535.26252.47449.38600.79684.910362.11029.11652.12072.12490.12880.13164.13448.13713.13918.14121.14311.14463.14612.14753

'4868.

14981.15088.15177.15264.15347.15413.15480.15576.15683.15789.15851.15911.15965.16019.16072..16125.16176.16223.16270.16317.16364.16084.15788.15506.15237.14980.

SZ68183.62041.56169.50803.48572.46328.44230.43011.41793.40667.39932.39199.38521.38043.37567.37125.36795.36467.36159.35920.35683.35457.35278.35099.34927.34788.34649.34513.34401.34289.34177.34085.33993.33898.33804.33725.33648.33572.33496.33426.33362.33299.33235.33173.33116.33060.33004.32948.32892.

PreparedReviewed

By: A.M. MillerBy: H.T. Harrison

Date: 2 95

Date: 2 95 Page: 25


TABLE 6.8, LOSS OF SECONDARY PRESSURE, P=200 PSI

S0.00000E+000. 119590.239180.358760.478350.597940. 717530.837110.95670

1. 07631. 19591. 31551.43511.55461. 67421.79381.91342.03302.15262 '7222.39182. 51132.63092.75052.87012.98973.10933.22893.34853.46803.58763.70723.82683.94644.06604.18564.30524.42474.54434.66394.78354.90315.02275.14235. 26195. 38145.50105.62065.7402

SX-5205.0587.395836.89361. 39958.310290.10363.10092.9703.69218. 78598.47929. 17239.16491.25747.05000.94228.63502.82767.62036.51355. 7663.808. 7152

-616.39-1248.7-1812.4-2368.7-2915.8-3393.9-3876.5-4314.1-4701. 6-5092. 1-5422.5-5749.9-6073.0-6325.6-6566.3-6806.8-7026.7-7172. 2-7316.9-7460.9-7604.2-7816. 6-8028.3-8233.2-8431. 3-8622:6

SY15781.12266.9310. 98486.69430.210146.10524.10362.10107.9732 '9133.38489.47802.17019. 96235.65437.84599.93801.62992.42182.81422.8654.06

-76.898-773.97-1474. 9-2101.0-2715.4-3315 ~ 1-3835.6-4359.0-4853.0-5312. 7-5771.4-6135. 3-6492.4-6849.9-7122. 2'-7380.6-7639.3-7877.5-8031. 6-8186.8-8343 '-8500.8-8385.2-8254.9-8132. 8-8019.2-7913.9

SZ98478.82490.68060.56501.50752.45286.40344.36430.32662.29217.26146.23197.20462.17888.15461.13164.10941.8912.16934.65031.03296.11579. 5

-22.322-1522. 1-3010. 1-4329.8-5611. 0-6851. 7"7933. 1-9009.0-9994.7-10897.-11795.-12524.-13236.-13951 ~

-14503.-15023.-15539.-16014.-16330.-16643."16952.-17257."17369.-17463.-17554.-17643.-17729.


Date: 2 95

Date: 2 95 Page: 26

llmml5lmlllllilllmmllm~<NINNIIIIIIIIuNllllmlmlllllllllllllllNlllllllmlll+>~IglllllllllÃ~~lllllllllllllllagllmlllllllESagllllglNIIEErIllllllmllNIERllllmmllllllmRNSXIXXXXXXXXXXlIOSQl)llmXQXXi550IfffffRffffIINSRrarararraaasssRQraaararaaar! Rs88Raarrrrrrra5%8%%RrrraaaararassoRiaraaaaarraa558%raaaaraaaara sass~aaaararaarrsRRRsrrrrrrarrrsw5%%~rrrrraraaaarrar~raarrrara armer eNNIIIIINNma

BRW NUCLEAR TECHNOLOGIES **BWNT NON"PROPRIETARY** 32"1235127-01

"Intensionally Left Blank - Contains BWNT Proprietary Information"

Figure 6.2, Stress Path for Flaw Plane


Date: ~295Date: 2 95 Page: 28


m-e I--o„„ggSgZ >r~Q- I I

cnl-cu0cnujm0- j'I-I-Q ~ ~Z~gZOe~OI-DR<0040oQ.Q.cONI-Q.ZZ

ZO0KO

CS ~ ~ Q~ann/OOOOs~)sr~+

QBU.lLILLU

00

O

a0)H

ec

O

40WOX

0 CO

P

Figure 6.3, End of Heatup Stresses (psi)


Date: 2 95

Date: 2 95 Page: 29


v)l-ol0v)ulcl+l-ZO(yj~OI-Z <0040oCLO.SNl-O.ZZ

ZulOOKO

CS ~ ~ Q+u)u) u)0

v- g OO(5PIl I I IZ)Bu.u.u.ujNOXO-NO

O

I-N g)g Hec

o gc

O

CQG.

I

OCLul

8

Figure 6 ', 53'F Step-down Stresses (psi)


Date: 2 5

Date: 2 95 Page: 30


CO

geP)Z < cOQ. g g

ZOg)9QI-D><QQCOSQ.Q.V)NI-Q.ZZ

OOx0

CS ~ ~ .Qv OOOOspssag

O

aU)

aei

O

'V cv

Pi 5 5 cv00

0'igure

6.5, 53'F Step-up Stresses (psi)


Date: 2 95

Date: 2 95 Page: 31


ZO"90I->K<00c(0v-Q.o.cOU)I-0 zz

tllCIQKO

O+eee0r I OOO<If I I IP

NM

CO

n

40

OI

Hei

O

40WOX n n

Figure 6.6, Steady State 653'F (Tref 70'F) Stresses (psi)


Date: 2 95

Page: 32

BEcW NUCLEAR TECHNOLOGIES **BWNT NON-PROPRIETARY** 32-1235127-01

~X ~

f-%O~<~~ i~CfCfZO"BOf-OR<00<0 a.a.rnrnf=a.aa

OO

O

CI ~ ~ . Q'nnng

v- g OOCjPIf I I lg

M V)N

O

aN

H

O h 4Pt

A5

O

COQ.COOlC)

E5

0.z0900O

Figure 6.7, Cooldown Stresses (psi)


Date: 2 95

Date: 2 95 Page: 33


g~PAZ~ ~t-~>+ I I

CZP-Q.Q.V) gP0. ZZ

zOOKO

nu? u? u?OK~ I OOO)~sang)-U.U.U.UlNOXO-NO

0-N(OM

CO

O

~0

MH

C4

4O

o oX

cv

O

V)

CDI

Z090O

0O

eFigure 6.8, End of Cooldown Stresses (psi)


Date: 2 95

Date: 2 95 Page: 34


Z0~90gg><OQCOSQ.O.V)Nl-fLZZ

ZLllOOKO

O ~ ~ .g5 g OOQaI~ I I ~ P

NM

aO

40

MH

C5

O

o 8 r g g e 959

Figure 6.9, Steady State 653'F (Tref = Tunif) Stresses (psi)


Date:~2 95

Date: 2 95 Page: 35


<X "

Rogg90PD><00<0 O.O.COCOI-O.aa

ZLUClOKO

~IAIALOQ~ g OOO)~a I Sg

N 0- rCO

aO

Hcv

O

COCL

8I

CL

UJKDCOCOLCj

K

C0R0OLljCO

0COCO0

Figure 6.10, Loss of Secondary Pressure Stresses (psi)


Date: 2 95

Date: 2 95 Page: 36

BEcW NUCLEAR TECHNOLOGIES **BWNT NON-PROPRIETARY** 32-1235127-01

7.0 ANSYS 5.0A Verification

The ANSYS analysis code, version 5.0A, was verified using closed form solutionsfor hoop stress in a sphere and stress concentration factors. The followingcomparison of finite element (FE) stress results and closed form solutionsindicated that the software provided accurate results. Therefore, ANSYS BOA was

verified for this application.

Finite Element Results from Table 6.7, Pressure 2250 psiaDistance Hoo Stress Sz

0.04.3052

6818333648

Hoop Stress

Ref. [5, Table 28 case 3a.]e ~ pr/2te = 2250 (120. 5) / [2 (4. 094) ] ~ 33, 112 psiCompared to 33,648 psi (FE), h% = (33648/33112 - 1) (100%) 1.6%

Stress Concentration at Hole

SCF = a,,/a,,» 68183/33648 2.026 (FE)

Compared to 2 (from Section A3.3), h% (2.026/2 - 1)(100%) 1.3%


Date: 2 95

Page: 37


8.0 References

1) ASME Boiler and Pressure Vessel Code, Section III, Division 1,Appendices, 1986 Edition with no Addenda.

2) BWNS Document No. 51-1155656-00, "Standard Correlations for NaturalConvection". "BWNT Proprietary Document."

3) BWNS Document No. NPGD-TM-500, "NPGD Material Properties ProgramUser's Manual", Rev. D, March, 1985. "BWNT Proprietary Document."

4) Not used.

5) Young, W. C., "Roark's Formulas for Stress & Strain", 6th EditionMcGraw-Hill, New York, 1989.

6) DeSalvo, G. J. and Gorman, R. W., "ANSYS User's Manual for Revision5.0", 1992, Swanson Analysis Systems, Houston, Pennsylvania.

7) BWNT Document 32-1235128-00, "FM Analysis of St. Lucie PressurizerInstrument Nozzles". "BWNT Proprietary Document."

8) BWNT Document 38-1210588-00, "Pressurizer Instrument Nozzles, FM

Design Input," for St. Lucie Unit 2, dated 11/11/94 (FP&L Number JPN-PSLP-94-631, File: PSL-100-14).

9) 'Florida Power & Light Drawing No. 2998-19321, Rev. 0, "Top HeadInstrument Nozzles Repair".

10) 'Florida Power & Light Drawing No. 2998-18709, Rev. 1, "PressurizerGeneral Arrangement".

*References marked with an "asterisk" are retrievable from theUtilities Record System.

uthorized Pro'ect Manager's Signature


Date: 2 95

Date: 2 95 Page: 38


9.0 MicroficheMicrofiche are not included in this document because they contain mathmodel which is BWNT Proprietary. However, for completeness the listing ofthe computer runs as contained in Rev. 0 of the document ("BWNT

Proprietary" ) are given below.

FILE NAME

THERMAL.OUT

STRESS . OUT

LPTHERM. OUT

LPSTRESS.OUT

STEADYST.OUT

ENDCD.OUT

DESCRIPTION

Composite transient thermal runs including 100 'F/hr Heatup,53'F Step-down, 53'F Step-up and 200 'F/hr CooldownStress runs for the composite transient in "THERMAL.OUT"

Loss of pressure thermal runStress run for the Loss of Pressure transientSteady state stresses (Tref Tunif 653'F)Stress run for the end of the 200 'F/hr Cooldown.


Date: 2 95

Date: 2 95 Page: 39

', lt 8 A

0

0

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