ML20058K474

Summary of 900614 Meeting W/Epri in Palo Alto,Ca Re Thermal Stratification Related Issues.Meeting Handout Matls Encl

ML20058K474
Person / Time
Issue date:	06/27/1990
From:	Su N NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Rosenthal J NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
References
NUDOCS 9007060144
Download: ML20058K474 (52)

Text

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JUN 2 71990 MEMORANDUM FOR: Jack E. Rosenthal, Chief Reactor Operations Analyses Branch Division of Safety Programs Office for Analysis and Evaluation of Operational Data THRU :

George F. Lanik, Chief Reactor Systems Section GE & CE Division of Safety Programs Office for Analysis and Evaluation of Operational Data FROM :

Nelson T. Su Reactor Systems Section GE & CE Division of Safety Programs Office for Analysis and Evaluation of Operational Data

SUBJECT:

TRIP REPORT - MEETING WITH EPRI ON JUNE 14, 1990 On June 14, 1990, George Lanik and Iqyself met with Dr. Jone Kim of EPRI and Mr. Arthur

Deardorff of Structural Integrity Associates,

Inc. in Palo Alto, California, to discuss thermal stratification related issues. As you are aware, EPRI is conducting a generic program named TASCS (Thermal Stratifica-tion, Cycling and Striping), which is sponsored by all PWR and BWR owners groups. Dr. Kim is the project manager and Mr. Deardorff is the principle consultant. The purpose of this meeting was to exchange technical informa-tion and te learn their evaluation results of the German experimental data.

Copies of hand-out materials are attached.

Dr. Kim presented an overview of the TASCS project.

The significant aspects of his presentation include the following:

1.

Because of the extensive interest of the owners groups, the project has extended its completion date from December,1991 to January 1993. Dr.

Kim indicated that the extension was requested by the owners groups to ensure that there will be sufficient time to develop applicable guide-lines to deal with the thermal stratification issues, j

2.

The task of collecting operational and ex)erimental data was recently completed. The data are being evaluated ay EPRI consultants.

Evalua-tion of the German data has been completed and the results will be i

discussed in this meeting.

S ges l

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foo7o6ci44 900627 c-gDR Topnp ex7 egg;

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Jack E. Rosenthal 3.

Two laboratories of Electricite de France (Edf) are independently conduc-ting experiments on thermal stratification phenomena, in particular, EdF is very much interested in the effects of turbulent penetration on thermal stratification which was also identified in our special study resort. The turbulent penetration experiment is partially supported by EP U.

Mr. Deardorff presented the results of evaluation of the German data.

His presentation is sumarized as follows:

1.

The German experiments were primarily aimed to determine the effects of thermal striping. The German tests are large-scale simulated feedwater flow with wide range of flow rate. Many thermal probes were installed to provide extensive temperature measurements (axial and azimuthal) along the tested aipe. Significantly, they measured the inside metal tempera-tures and t1e fluid temperatures in the interface with the metal.

2.

Methodology for thermal striping fatigue analysis was established to determine the effects of thermal striping on pipe material fatigue. The methodology includes criteria to calculate thermal stresses, wall tempera-ture spectrum, fluid velocity, and fatigue usage factor.

3.

The evaluation calculated fluid velocity and established the relationship between fluid velocity and fatigue usage factor. Results of the evalua-tion indicate that fatigue usage factor increases with increasing fluid velocity. This means that higher flow rate in pipe enhances the effect of thermal striping on pipe material.

4.

Since the flow rate of the pressurizer surge line is normally low, the fatigue usage factor is approximately nil based on the evaluation indicated above. Therefore, it is concluded that the stresses resulting from thermal striping are insignificant and have minimum contribution to the overall stresses from thermal stratification.

Finally, we presented the status of NRR review activities and our follow-up study. We also mentioned the proposed technical assistant program to be conducted by ANL to analyze thermal stratification for surge line. Dr. Kim seemed very interested to our program because develo) ment of an analytical method to predict thermal stratification is one of t1e objectives of the EPRI program. He expressed his desire to discuss the analytical results when they become available. We expressed our concerns that the German data included only steady state flow conditions and high flow rates.

We also expressed our interest in seeing the results of their analysis of the transient effects of inflows and outflows.

l

i e

Jack E. Rosenthal l We all thought that this meeting was mutually beneficial. Thermal stratif.1-cation has become of international interest. More experimental results are expected from the French ar.d the Japanese tests.

Further EPRI evaluation results of operational data is scheduled to be completed by the end of this year. We will keep each other closely informed about development of this matter.

Odginalegnedby Nelson T. Su Reactor Systems Section GE & CE Reactor Operations Analysis Branch Division of Safety Programs Office for Analysis and Evaluation of Operational Data

Enclosure:

As stated Distribution:

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, Central File' ROAB R/F" DSP R/F AE00 R/F NSu Glanik JRosenthal TNovak EJordan Dross CCheng, NRR LHarsh, NRR 9

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m EPRI TASCS (Thermal Stratification, Cycling and Striping) Project I

Presented by j

Jong H. Kim Project Manager Nuclear Power Division i

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i Safety Performance Program iin v ein u fris,

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3. Perform testing and analysis to develop models and correlations to l

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5. Categorization of Geometries and Mpchanisms

6. Evaluation of information vs. Needs

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COORDINATION WITH UTILITIES 1

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- Owners Group i

- TASCS OG Advisory Committee formed

- PWR OG meeting at EPRI, May 4,1989 j

l

- PWR OG meeting at Washington, DC, July 6-7,1989 4

- OG Advisory Committee Meeting at EPRI,~ December 8,1989

- OG involvement in Phase 1 tasks

- OG Advisory Committee Meeting at Chicago, March 21,1990 t

- Technology Transfer

- Utilities workshop i

1

- Timely dissemination of interim results s

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Safety Performance Program 06:1V/.liiK'C.lS 7

mamme-EPRl/NPD s

DELIVERABLE PRaDUCTS Guidelines in the form of Reference Manual or software

- Identifying systems and locations where TASCS may occur

- Determining thresholds for TASCS

- Case studies

- Description and categorization of mechanisms

- Data and models for predicting and accommodating TASCS Other documentation as deemed necessary

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--- Safety Performance Program

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N Summary and Conclusions l

1 l

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• Thermal stratification, cpeling and striping are an important current issue in the U.S.

• The issue is of generic nature and can potentially affect many domestic and foreign plants I

• A comprehensive, coordinated R&D effort is underway with sponsorship from liPRI and NSSS Owners Group l

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i Safety Performance Program l

071 \\'/li ll; /('lS I i

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I EVALUATION OF HDR TEST DA~A i

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Ar+ Deardorff Structural Integrity Associates c

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May 1990

' STRUCTURAL INTEGRITY a asa assocaras. mc o

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DISCUSSION TOPICS TEST FACILITY TEST MATRIX l

TYPICAL TEST RESULTS STRIPING FATIGUE ANALYSIS i

METHODOLOGY DEVELOPMENT OF WALL TEMPERATURE SPECTRA

_l VELOCITY / FLOW RATE EFFECTS APPLICATION OF METHODOLOGY TO TYPICAL STARTUP CONCLUSIONS i

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IEMR-I5 SIS Figure 1.

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Table 1 i:

Nominal Test Conditions (Reference 2)

TEST PRESSURE'. TEMPERATURE F

' DENSITY LbdFt3 COLD FLOW No.

psi.-

HOT ~

COLD HOT COLD gpm T33.14

'94 315 81 56.9 62.2 16 T33.15' 93 316 68 56.8 62.1 107 T33.16' 94 314 113 56.9 61.8 166 T33.17 321 414 79 53.1 62.2 9

T33.18 332 417 96 52.9 62.0 107 T33.19' 325 417 130 52.9 61.6 204=

T33.25-1

• 638 486 95 49.8 62.0 32 T33.25-2

• 638 486 95 49.8 62.0 120 T33.25-3*

638 486 95 49.8 62.0 207

• Evaiuated in this report i-89 t71AD l

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'~.; ion II, Test T33.25 SIR-89-050, Rev. 0 21 89*172AD

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THERMAL STRIPING FATIGUE ANALYSIS METHODOLOGY I

a THERMAL STRESSES DETERMINED l

BASED ON " SKIN" THERMAL STRESS S,n = 1 E

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CYCLES PER HOUR AT LEVEL i i

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DEVELOPMENT OF TEMPERATURE L

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EACH OF WALL TEMPERATURE TRACES i

EVALUATED i

SPECTRA DEVELOPED USING OVERALL ORDERED RANGE (OOR) CYCLE COUNTING 1

i METHODOLOGY

- Appropriate for Fatigue Analysis

- Determines Number of Ranges Exceeding Set Screening Levels CONSERVATIVELY BASED SPECTRA ON LOCAL (T

-T eorroy )

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SIR-89-050, Rev. 0 35 89-178AD

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k Table 2 Thermal Striping Spectra Cumulative Temperature Cycles per 240 Seconds Exceeding Screening Level SCREENING '

TEST" TEST 1

TEST, TEST-TEST BWR LEVEL, %

• T33.15 T33.16 '

T33.19 T33.25-3 T33.25-2 Ref.(4)

+

50.0 0

0 0

0 0

0 s

49.5

,0 0

0 0

0 1

48.5 0

0 0

1 0

2 47.0 0

2 0

1 0

3 44.0 0

5 0

2 0

5 40.0 0

13 0

3 0

10 35.0 0

19 5

5 0

18 30.0 0

26 10 14 0

28 25.0 1

32 17 33 0

40 s

20.0 14 42 31 70 0

70 15.0 39 50 43 100 8

150 5.0 105 71 89 159 135 650 l

1 i

l

, -i :

• Percent of Top-Minus-Bottom Temperature Difference l1 89-179AD

O, e' Table 3 Thermal Striping Loading Spectra Temperature Cycles per Hour Exceeding Screening Level Temperature -

TEST TEST' TEST TEST TEST-BWR -

Range T33.15 '

T33.16 :-

T33.19 T33.25-3 T33.25-2 Ref.(4)

(% of Maximum)

• 49.75 0

0 0

0 0

15 49.00 0

0 0

15 0

'15 47.75 0

30 0

0 0

15 45.50 0

45 0

15 0

30 t

42.00 0

120 0

15 0

75 37.50 0

90 75 30 0

120 32.50 0

105 75 135 0

150 27.50 15 90 105 285 0

180 i

22.50 195 150 210 555 0

450 17.50 375 120 180 450 120 1200

.i 10.00 990 315 690 885 1905 7500

• Percent of Top-Minus-Bottom Temperature Difference 89-180A0

FATIGUE USAGE PER HOUR Steinlese Steel - T(Lop) = $80 F

+ T33.16

+ T33.19

'A T33.25-3

~

x BWR

? T33.25-2 10 '

5 2

, - i.

g

.o D

e 36

.c 10 '

-6 0

100 300 500 T(too) - T(bottom). F l

l Figure 19.

Fatigue Usage per Hours for Test and BWR Spectra SIR-89-050, Rev. 0 36 89*193AD i

.)

i VELOCITY / FLOW RATE l

EFFECTS i

• HDR TESTING DESIGNED TO EVALUATE i

FEEDWATER NOZZLES

- Flow > 100 gpm for temperature oscillations i

l

• ACCOUNTING FOR SURGE LINE FLOW r

RATES MITIGATES LOADS s

• BOUNDING REVIEW OF DATA JUSTIFIES I

l

. ELIMINATION OF HIGH AMPLITUDE PEAKS I

BASED ON FLOW RATE i

l I

t a

j.

~ f 8 9-181 A D

CUMULATIVE NUMBER g_

0F RANGES:

=

8 max.

n_

A 1/ min

~

A

~

=

\\7 3/tdn

~

=

O 6/rdn 9.ef 38.

So-is W

25

^

"L

=

gn-3 T33.15 16

^

W c-

^

5

,^

m

7. v

~

e.

6 10 +

~

9

^

,4 4

4,5 9...

i i

i i

.0 25.0 50.0 75.0 100.0 125.0 150.0 175.0 200.)

225.0 250.0 275.0 AVERAGE COLD WATER VELOCITY lil MM/SEC

\\

IIDR-TEMR TEST SERIES: NORMALIZED NEAR-WALL FLUID TEMPERATURi! FLUCTUATIONS AS A FUNCTION OF COLD WATlitt VELOCITY (numbers at symbols refer to individual experiments)

I 89-182AD

=

c_

D '2

fl~

-CUMULATIVE NUMBE2 0F RANGES:

y_

El nm.

A 1/miU

~

V 3/inin LaJ O 6/ min o

Be w

^

E g

m n _.

a a

[

9# hb 7

b= '

f3 n

7 23 g

m 6

T33.15 5

~I

'I ^

~

4 I

/g 109 q_

I I

I I

I I

I I

I I

.0 25.0 50.0 75.0 100.0 125.0 150.0 175.0 200.0 225.0 250.0 275.0 AVERAGE COLD WATER VELOCITY IN MW/SEC llDR Tl!MR TEST SERIES: NORMALIZI!D INSIDE SURFACli TilMPl!!tATUltl! Fl UCTUATIONS AS A FUNCFION OF COI.D

-WATl!R VELOCITY (numbers at symbols icfer to imlivi<lual experiments) 89-183AD a

,,.,,J.

1 i

Figure 8.

Maximum Relative Temperature Range Versus Local Velocity MAX THERMAL STRIPING AMPLITUDE Sosed on HDR Test Date 50 -

g C

O i

1 p

20 -

O C

l

-E l

1o -

a o

o C

0 0

0.2 0.4 0.6 0.8 LOCAL YELOC!TY (ft/sec) i 8 9 18 4 AD

.m t

Figure 9.

Relationship of Local Velocity to Nominal Velocity in Stratified Flow 4

J LOCAL VELOCITY RELATIONSHIP 1

s.. w.n a r o.i.

1 O.9 -

g 0.8 -

0.7 -<

g

0.. -

1 0.s -

o o 0.4 -

C g

D 0.3 -

O 0.2 -

0 0

0.1 -

0 e

4 4

i 0

0.1 0.2 CJ 0.4 Nominal wetar veiecity (ft/sec) 8 9 18 6 A D m

m

.. m

,.r m-. - _,,,.. - -,

._y.

..y,

q

)

Figure 10.

Thermal Striping Fatigue Usage as a Function of Nominal Pipe Velocity FATIGUE USAGE PER HOUR

-2 Steinlose Steel - T(top)=450 F C

V = 0.05 Ft/sec

+

V = 0.1 Ft/sec 0

V = 0.2 Ft/sec A

V = 0.3 Ft/sec 10-3J f

a//

i p

104_

jl

/

/

k

//

5 d

//

t

/ '

/

10~5 j

i

/

I 10-6

/

i i

i 1M 3M 20 T(top) - T(bottom). F ~

l 6 9

• 18 6 A D

e i

TYPICAL PLANT STARTUP APPLICAT Oh

• DATA FROM SAN ONOFRE STARTUP USED - 10 HOURS

• FLOW VELOCITY BASED ON SPRAY FLOW AND PRESSURIZER LEVEL CHANGES i

e MAXIMUM NOMINAL VELOCITY < 0.1 f t/sec FATIGUE USAGE = 0 BASED ON l

ABSOLUTE VELOCITY HISTORY

- Actual Velocity u = 0.0 L

- 2 x actual

• u = 0.0 l-

- 5 x actual

• u = 0.000034 l

- 10 x actual

• u = 0.00023

• to show sensitivity 8 9 18 F A D l

---

r-

- - - - - - - - - -^ ^ - - - - -

^ ^ ^ '

1, I

^

T LOCAL THERMOCOUPLES sat LEVEL

-v --

~

(

PRESSURIZER i

(

\\/

./

,/

o I"

T105 top POINT 2

/

h 4 TEM 4\\\\%%%%%MRWMREit 4

l J

Tbottom RCS T

• hot l

i SONGS U. NIT 3 SURGE LINE SCHEMATIC 1

SHOWING FLOW STRATIFICATION AND LOCAL INSTRUMENTATION i

i i

89*180AD

,(

e f

SAN ONOFRE UNIT 3 PZR HEATUP PDt MIEEOURE - P102A 2J 1,2 -

2.1 -

3-IJ -

1J -

1.7 -

k 1.4 -

in 14 -

1 1A -

1J -

1.2 -

1.1 -

E i-t 0.0 OJ -

g/

17 -

16 -

04 -

OA -

/"

ce+4 i

0.7, -

i i,

IJ.000 1.000 2.000 3.000 4J00 M.3 e 4J00 7.000 L300 2.000 10.000 Todt (HOURS)

SAN ONOFRE UNIT 3 PZR HEATUP nn mannies M

l 680 -

A1

^

T^-

((

,.%M t

I 400 -

i

(

e i

m-o m

a

\\

5 I

v g

5 i

m-s'E

\\

/

g 5

• 1________ N..,

r

--g s00 -

1 g[

i A

t

. 1 89 189AD faTJ i

i.

i.

i-i i-i 4,

0.000 1.000 2.000 3.000 4.000 1 000 4.000 7.000 A.000 3.000 1C YJO

. 3 A -

x ? W

. e.

= -

t, l

)

SAN ONOFRE UNIT 3 PZR HEATUP S/8/05 (0000 - 2100 655)

I as.s I ss.s I

• • ' 'l

'.I ss2 sai t

sts -

p 3L8 -

314 -

f sLa -

l' 32 -

g a.

sta.

31J M

Is

= < < -

f7 nt 31.2 -

3, _

j s.[

y i

30 -

t 30,,.......

.. -r,,.mm,,,m,vn 0.000 1.000 2.000 3.000 42

.J00 LOOO 7.0G0 LOOO 9.014 19.000 TnE (69ts)

SAN ONOFRE UNIT 3 PZR HEATUP St#10E t.NE POWT 2 400,

g 4701 kl 440 -

(

W M

J 440 02 e

43,.

~

L-420]

07

)

07" b

l f

• ~I f

t4 4L J

.T70 4

q, N

g

(

• +:::: 4 310 -

f v4 s00 -p ij

• f g

230,

.i....,

i..

0.000 1.000 2.000 3.000 4.000 5.000 L000 7.000 LOOO 9.000 10.000 89a190AD

+

TCP 70 t

L TT*W T",

e j e

SAN ONOFRE UNIT 3 PZR HEATUP 8/8/04 (oDoo - tion MRS) n.s i

"1 f

314 -

n.2 I l{

n -l n.J

/

J e

mi

}

32.4 I

a.2 \\

n -)

N M

si.s -)

[\\

i

=

l c

31.4 -

\\

og g 31.2 -

+

]

og g

2, _

l

+

on

/

J SoAx...]re,,,,,,,,,,,,,,,,,,v,,..........,,c....,

g g o.aos

i. coo 2.ooo 3.ooo 4.ooo s.ooo s.ooo 7.ooo

..ooo

..ono io.ooo T1WE (HMS)

SAN ONOFRE UNIT 3 PZR HEATUP l

SURot UNE PoNT S 68o oS (w o7 c4 soo,

=-

C I

a-o2 os

}

I o

{

g,,

c1 1

i u

g

~R4 m-

+

A/

/

g g ^^ :4

• ~

d g

,g : M*p W,4,E 3ao -

m 23o ;.

a e. t e ig o.ooo 1.ooo 2.ooo 3.ooo 4.ooo 5.ooo 6.ooo 7.ooo 4.ooo 9.aoo to.ooo TIME (HOURS)

+

Top TC 4

LTW T;

-u.

Figure 12.

Surge Line Nominal Velocity During Startup SAN ONOFRE UNIT 3 PRZ HEATUP e.:, ;

c.:s -

0.07 +<

j o.c6 -

0.cs -

O.04 -

0.C3 -

p J

e.e2 -

0.01 -

i 0

M 9

~

0 E

I

,g

-0.:s -

8)

~

-o.04

-C.Cs -

-0.C 6 -

-0.07 -

J "O 00 0

2 4

6 8

10 wt00ts) 8 9

• 19 4 A D

l i

CONCLUSIONS l

l i

I

?

THERMAL STRIPING MAGNITUDES FOR SURGE LINE CONDITIONS VERY LOW I

c FATIGUE EVALUATION INDICATES i

USAGE = 0 l

l SOME ADDITIONAL JUSTIFICATION l

REQUIRED TO GENERALIZE FOR OTHER PIPE SIZES I

.I l

I

?

l i

k j

8 9 19 2 A 0 l

,--w o,-

4--ap.

,ewn-

--m g

y-v

e Q

'O o

o DEVELOPhtENT OF A THERh! AL STRIPING SPECTRUhl I

FOR USE IN EVALUATING PRESSURIZER SURGE LINE FATIGUE A. F. Deardorff Structural Integrity Associates, Inc.

3150 Almaden Expressway, Suite 226 San Jose, CA 95118 W. Hafner and L. Wolf Battelle-institut e.V. Frankfurt Am Romerhof 35, D-6000 Frankfurt, West Germany J. H. Kim Electric Power Research Institute 3412 Hillview Palo Alto, CA 9003 ABSTRACT t

= surge line nominal Guld velocity, meters pc,

second Data taken from the German !!DR test facility have been evaluated to understand the therrnal-hydraulic k

= number rf spectral levels in the loadini phenoment which occur during conditions of straticed Dow in a pressuriser targe line. The tempersture oscillations in the spectrum Guid layer between the hot and cold Guids can approach the

r. i

= number of cycles per hout in loading spectrutt maximum possible top-to-bottom temperature differential.

The temperature oscillation at the pipe wall is considerably for spectral level l less than that in the Guid, being no more than about 50 Ni

= allowable number of cycles for the strest percent of the maximum possible temperature difference. The location of this Duld interface changes with changing Dow rate amplitude associated with spectrallevell in the pipe. At lower Oow rates, the ma temperature Ductuations decrease significantly. gnitude of the S ig

= alternating stress amplitude, ksi The ordered overall range approach

• emperstme at bottom of th pipe,'F uns used to determine pipe sur[ ace temair cycle countinbuctuation rature Ti

= temperature at top of pipe, 'F spectra.

Stress analysis was conducte to determine the fatigue usage resulting from the developed spectra.

This ATp.p = peak-to-peak amplitude of the temperature evaluation, conducted for typical plant startu conditions (s rge line temperatures and Dows), p operatin6 cycling at each spectral level, ' F shows that thermal stri ng fatigue usage will be minimal. The primary u'

= fatigue usage per hour mitigating ef ect is that the expected Gow rates in the surge line are much lower than those from the German tests where INTRODUCTION higher striping magnitudes were typically observed.

NOhlENCLATURE NRC Bulletin 88-11 required that the effects of strati 0ed Gow conditions be evalur.ted in pressuriser surge j

a

= instantaneous coef0cient of thermal expansion lines, including the effects of thermal striping (USNRC,1988).

To perform this evaluation, a loading definition is required to j

based on the mean temperature of the cycling, determine the thermal stresses and number of temperature in/in' F oscillation cycles which result during conditions of stratined Dow.

This issue has been addressed in a series of tests v

= Poisson's ratio = 0.3 performed in Germany (Wolf et al.,1987). Althou h the German tests were speci0cally designed for evaluation of PWR di

= amplitude from the temperature spectrum, at and BWR feedwater nozzles, the piping geometry, materials spectral level l and conditions tested are equally applicable to PWR pressurizer surge lines.

5.u = maximum amplitude Results of the most representative tests were chosen for E

= modulus of elasticity from the fatigue curve, analysis. In this paper, the test facility is brie 07 described.

i ksi (28.3 x 103 for austenitic stainless stel)

Typical test results are described, as an aid to understanding the phenomena involved.

A thermal loading spectrum is described. Based on the resulting loading spectrum, analysis

(

o i

o o

a was coaducted to assess the severity of thermal striping in Figure 3 depicts the temperature time history of both a pressuriser surge lines.

pipe surface temperature and a Guid temperature at 60 degrees from DDC. It is apparent that the temperature variation TEST CONFIGURATION measured at the pipe surface is smaller than the variation in the Guid. This is expected due to the Dnite heat transfer The !!DR test report p'ovides a detailed description of coefficient and thermal inertia of the pipe wall. In additien, the test facility and test matrix (Schygula, et al.,1986). The the Guld temperature range during thermal striping is experirnental test loop consists of a pressure vessel connected signi0cantly less than the total temperature range available to heating and cooling loops and a pressuriser. The piping and between the hot pressure vessel water in the top of the pipe vessel test configuration is shown in Figure 1. It consists of a and the relatively 'Jer water in the bottom of the pipe.

6427 rnm (21.1 ft.) length of horir.ontal 397 mm (15.G in.) ID by 16.!mm (.63 in.) thickness stainless steel pipe connected to To more closely examine the temperature ranges a controlled source of cold water for feeding the hot pressure associated with the Guld and the metal surface, Figure 4 shows l vessel. Cold water was slowly injected from below through a 7 25 seconds of terrpera ture time history for the two m:ter long vertical pipe section connecting to the horizontal therrnocouples shown in Figure 3.

It can be teen that the pipe through an elbow. Two instrumented sections were rnaximum metal temperature range is about 60'C (90'C to installed in the horizontal near the vessel, at 150'C) and that the maximum Guid temperature targe is approxienstely 22M mm (7.2 ft.)pipeand apptcximately 4400 rnm about 130'C 60* C to 190'C).

For this particular time (14.4 ft.) from the open pipe end in the vessel. The two history, the O d temperatyre range was about 50 percent of i

ir strumented test sections induded thermocouples around the the total temperature range between the hot and cold Guids.

circumference (,f the pipes out:ide pire surface sensors),(including unid, and inside and The metti ternperature rarige ws: about 30 percent of the overall temperature difference. Figure 5 shows a frequency I spectrum for the fluid temperature and derponstrates that a TEST M AT'l!X multitude of frequencies m present, mainly with frequency content less than 2 cycles gr second, i

Table i summarises the test matrix for the series of

=

tests to simulate PWR steam generator conditions. This test TilERMAL STRIPING SPECTRUM DETERMIN ATION series was conducted with the vessel end pipirig completely opzned to the vessel, such that maximum thermal strati-To deOne surface strmes due to high frequency thermal

.fication could be achiev?d. This con 0guration was shown to striping, f cycles per unit of time exceeding discre produce the most severe thermal striping and is bdieved to be number o wv conservative for determitation of pressuriser surge line required. To determine this spectrum, the ordered overali theimal striping loading.

range OOR) c and S(tephens, ycle counting approach has been us?d 1980.

For each test, these spectra were TYPICAL TEST RESULTS determined for eac of the surface thermocouples which exhibited signi'ieant temperature oscillation.

Test 33.25, conducted with three separate Cow rates, is discuued in some detail to provide the reader with a physical Table 2 and Figure 6 present the bounding cumulative understanding the phenomena observed. The pipe was initially spectra for each of the tests, based on a common set of Gll:d with hot water at 252'C (486'F) at a pressure of 44 bar screening levels. Also shown is the thermal striping spectra (638 psi).

Cold water Dow at approximately 30* C was based on a rapid cycling spectrum developed for BWR initiated at approximately 7.1 metric tons / hour 31 gpm at feedwater nortles (Watenabe,1980), adjusted to a 50 percert the beginning of the test. At about 950 seconds, t e cold w)ter a

rnaximurn temperature range (sntgested as the maximum in Dow rate was increased to 27.5 metric tons / hour (120 g m)

USNRC NUREG-0691,19R0). The table indicates the number followed by an increase to 47.5 metric tons / hour (207 gpm at of temperature ranges in 210 seconds of striping which execed about 1200 seconds, each of the screening levels. In Table 3, these spectra have been converted to temperature loading cycles per hour.

Throu out the test, hot water at the vessel temperature lied the to portion of the pipe sections and Cornparison of the results show that the test spectra varyin amounts of col water Olled the bottom portion from T33.16 and T33.25-3 are bounding. The results also de n ing u on the Dow rate. The Dow rate was never show that the maximum values decrease for tests with lower su Ocient to 11 the pipe completely with cold water. Fi ute 2 Gow rates. This conclusion is also reached by Geiss et al.

shows the effect of varying cold water Dow rate. At the owest (1989), where data is presented that correlates the maximum Dow rate (up to about 950 seconds), the lower pipe surface value of the normalized temperature difference with the cold thermocouples were essentially at the incoming cold water water velocity.

temperature and the top three pipe surfact thermocouples were near the hot vessel temperature. At the intermediate Dow rate FATIGUE ASSESSMENT between 950 and 1200 seconds), the level of the,old water in (he pipe section increased and settled near 75 degrees from To perform a fatigue analysis of thermal stripi g data, a t

60 degree thermocou(BD, as evidenced by the fact that the thermal stress spectrum must be determined rom the bottom dead center ple reased to about the cold water temperature spectrum. The following approach is used:

ternperature and the 75 degree thermocouple decreased to an E o ob intermediate temperature between the hot and cold Guids. At sm

. T Md

[g) the hi hest Oow rate (1200 to about 1600 seconds), the cold water evel increased past the 75 degree location and settled near the 90 degree thermocouple. The temperature of the The peak-to-peak temperature difference spectra is incoming cold fluid increased during the test due to limitations determined from in the fa'cility cooling abilities.

Tp p i x (T - T )

(2)

=

i b

Thermal striping behavior was observed at the two higher Dow rates. No thermal striping was observed at the instrument locations during the low Dow rate conditions.

.}o e At given top-to-bott;m temperature c:nditixs, the temperature oscillation range can then be a

o f tigue usage per hour can then be determined using AShlE determined as a fraction of the pressurir;r minus Code methodology (AShiE,1986). Dased on each alternating hot leg temperatute diffetence.

stress amplitude usociated with a given temperature oscillation range, the number of allowable cycles is determined.

3.

To deOne the temperature oscillation ranges and The resulting usage per hour is:

number of eyeles at each level, the bounding DWR spectrum of Table 3 is used. It is consertatively k

assumed that the cycles above the maximum

= { %n (3) relative range determined in step 2 are excluded u,

from the evaluation. The snaximum range for the

(=i remaining cycles is then taken as the relative The fatigue usage implication of the various thermd amplitude determine in step 2.

striping data evaluated in this study wu determined. Results This procedure has been applied in determining Figure are presented in Figure 7.

The computed fatigue usage was 10 which phows fatigue usage per hout as a function of nominal bued on a hot temperature of 650'F to maximite the pipe velocity and pressurizer to hot leg temperature coelDeient of thermal expansion, usuming that the coef0cient differential.

(For purposes of reader calibration, 2 g 14-inch Schedule 80 pipe is a velocity of 0.0075 ft/sec.)p of thermal expansion was determined bued on the nean of the top and bottom temperatures, hlaterial properties were based on 304 stainless steel.

Fall ue usage at a given plant can be Based on data rtesented by Griesbach t,t al 6

assessed from this data if a thermal duty mas for the approach has been used to piedict fatigue usage i(n pressuriter surge line is known (e g. pressuriter temperature surt,e line during startup conditions whtte e.ctual sutge line and hot leg temperature, especially during startup conditions).

velocities were determined based upon pressuriser level and density changes, and spray bypus Dow rate. Conditions EVALU ATION OF EFFECTS OF LOWER VELOCITIES during this startup are shown in Figures 11 and 12. Utilising this velocity data, and the above approach, the predicted The fact that essentially no striping was seen at the fatigue usage for the 10 hout period wu tero!

lower Dow rates suggested that thl rnay have signi0 cant potential for showing that the bounding spectrum was not To tr.st the s(nsitivity to velocit) (and rate of change of requited. Tip;ure 8 shows the relationship of the maximum pressurizer level), other similar evalattions were donc sting thermal striping amplitude in all tests to the local velocity of this data and arbitruy selocity multiplicts. Result! using the injected cold water (Geiss et al.,1989). A curve has i.een multiplicts of 2,5, and 10 on the surge line velocity resulted in drawn which bounds all data. Figure 9 is a similar bounding predicted fatigue usage of tero, 0.000031 and 0.000231 curve for relating the local velocity to the nominal velocity terpectively, for the 10 nour period.

based on Dow rate divided by total pipe area.

CONCLUSIONS Using these two curves a bounding relative amplitude can be determined as follows:

An evaluation of the most severe thermal striping data from the ilDR testing for PWR conditions has been completed.

For t t 0.0735 These data, combined with results of evaluations by Geiss et that PW)R pressurirer surge line thermal stripi A.n = 0.495 (4)

InsigniDeant.

Thl conclusion is based on the following observations:

For 0.00762 5 t < 0.0735 1.

The llDR testing was for Gow rates which would exist in a pressunter surge line for only extremely A.n = 5.577 9 + 0.085 (5) short periods of time. Nortnal expected Gow rates l

due to spray bypass Oow are expected to be much For v 5 0.00762 less than the minimum Dow rate observed to cause

(

any thermal striping. !!igher Oow rates due to pressuriser level changes would occur only on a 5.u = 27.89 t - 0.085 (6) transient basis.

Strictly speaking, these functional relationships would 2.

A fatigue evaluation, based on typical velocities only apply for pressuriser surge line piping similar to that tested in the IIDR facility. Ilowever, since the effect in smaller from a plant startup, showed that fatigue usage was negligible, piping would be to increue the velocities for equivaknt Dow rates,it is believed that the bounding curves of Figures 8 and 9 3.

The level in the pipe where thermal striping occurs are appropriate.

is very localized, and the level of the thermal ASSESSh!ENT OF RESULTS striping varies with Gow rate. Thus the area where thermal striping stresses occur is not constant with time.

Thus, there is additional inherent To utilire the above results, the following procedure is used:

conservatism since this evaluation usumed a single water level.

1.

The nominal pipe velocity history must be determined from the pressuriter spray now rate and 4.

The llDR testing wu with a pipe site and material rate of change of pressurirer level.

that is not unlike that which exists in PWR 2.

The appropriate equation of 4 through 6 may then pressurizer surge lines. Ilecause of the sirnilarity, it be used to denne the maximum relative range of is believed that the results of the testing can be thermal striping The history of the absolute generally applied for evaluatian of surge line thermal striping.

g' o

o a

o 5.

The cpen-ended pipe con 0guration to sim: late steam generator notries cas sho;n to produce the most severe striping. Actual pressuriter surge lines Table 1 are relatively longer and should offer more Nominal Test Conditions restriction to now. Thl should further reduce the tendency for interisce thermal oscillation.

Test entasvat 3tuesmatuet.r erwarty tasri s coto r6owl i

No.

p.f Hot CotD mot COLD gom -- t REFERENCES in u 34 ei ne u2 u"

f 3318' 93 sll H

64 8 et t 137 American Society of bicehanical Engineers, Boster tu u' sie us we si e in end Pressure Vessel Code, Section ill,1986.

E

'N C

'll

'y

,,I i n te-3ts att is0 st s ei s 304 Fuchs, !!. O. and Stephens, R. I., Afetal Potipue in tu ts.i-sie su n

os no n

Engineennt, John Wiley and Sons, New York,1960.

t u es t-sse see es se e s0 10 73326-3' 43e 4H tl at 8 ft0 20' Geiss, h!.; Wolf, L; !!1fner W.; llans) sten, E.t

'0*'""*5***'

and Talja, A.; " Temperature and Wall Strain Flactuations During the TEh!R Thermal Strat10 cation Tests at IIDR",

Trarnachon of 19th SAhRT Conference, (Volume F,183),

1969.

Griesbach T. J., Riccardelle, P. C., and Gosselin, aNo 2 S. R, " App!! cation of Fatigue bienitor :g to the Evaluation of

.hermal Striping $pectra

• *"**"* "** '";,8

,[j* o **"""*

Prenuriser Sur e Lines," Transaction of Post-SAfiPT M

Conference 14,1g89.

e>:anvaan its?

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