ML20212B576

Pressurizer Heater Incident,Task 832

ML20212B576
Person / Time
Site:	Rancho Seco
Issue date:	02/21/1987
From:	Schaefer R BABCOCK & WILCOX CO.
To:
Shared Package
ML20212B431	List: ML20212B427 ML20212B576
References
51-1167986, 51-1167986-00, NUDOCS 8703030590
Download: ML20212B576 (172)

Text

V

.D F

RANCHO SECO

~

PRESSURIZER HEATER INCIDENT TASK 832 B&W DOCUMENT No. 51-1167986-00 PREPARED BY:

J/ 07 REVIEWED BY:

5 C

APPROVED BY:

/b 4-E/Z'/07 Prepared for Sacramento Municipal Utility District 6201 S Street, P.O. Box 15830 Sacramento, CA 95852-1830 By Babcock & Wilcox Nuclear Power Division P.O.

Box 1260 Lynchburg, VA 24505-0935 1

G703030590 070224 DR ADOCK 05000312 g

PDR

.s EXECUTIVE

SUMMARY

This report describes an assessment of the expected condition of the Rancho Seco pressurizar considering the heater uncovering event of November 21, 1986.

The objective of this assessment is h

to evaluate the factors affecting the re-useability of the pressurizer following the abnormal event.

This assessment was based on an examination of conservative transient thermal calculations, criteria used to establish the acceptability of the component are based on engineering judgement considering the original material qualification temperatures and stress-relief temperature.

Table 2

summarizes the assessment of the majcr pressurizer components.

The maximum base metal and cladding temperatures were conservatively determined to be 9190F and 10020F respectively.

These temperatures are acceptable based on the established criteria.

Therefore, based on the results of the conservative thermal analysis performed, all components except the upper and middle heater bundles are acceptable for reuse.

The upper and middle heater bundles have been replaced.

Additional long term effects of the incident (fatigue usage factor increase) will be determined later.

Additionally, the calculations in Reference 5 show that the maximum temperature of the heater element at the diaphragm plate is 258F.

This value is significantly less than the normal operating temperature of a heater element at this location.

Therefore, the electrical connections to the heater elements were not degraded as a result of the heater bundle incident.

In conclusion, the effect of the heater bundle incident on the near term structural integrity of the pressurizer is acceptable.

2

~

TABLE OF CONTENTS PAGE EXECUTIVE

SUMMARY

2 1.

INTRODUCTION 4

2.

PRESSURIZER TRANSIENT ANALYSIS 5

2.1 SCOPE 5

2.2 DISCUSSION OF METHODOLOGY 7

2.3 RESULTS 13 3.

METALLURGICAL EVALUATION 21 3.1 SCOPE 21 3.2 RESULTS 21 3.3 DISCUSSION 22 4.

REFERENCES 24 LIST OF TABLES TABLE PAGE 1

Heater Bundle Transient 10 2

Pressurizer Metallurgical Assessment 23 LIST OF FIGURES FIGURE PAGE 1

Pressurizer Longitudinal View 6

2 Actual Pressurizer RTD Temperature 8

3 Pressurizer Upper Heater Bundle Heat Flow 9

4 Heat Flux vs. Distance From Centerline 14 of Heater Bundle 5

Pressurizer Shell Regions Analyzed 15 6

Pressurizer Heater Bundle Opening 19 Maximum Temperature 7

Heater Bundle Opening Thermal Contour Plot 20 3

U

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INTRODUCTION This report describes an assessment of the physical condition of selected pressurizer components and presents recommendations on whether the components can be reused or should be replaced or repaired before repressurization of the pressurizer.

The assessment and recommendations ars ' based on a

conservative interpretation of design information and conservative analyses of the transient effects over the period beginning at 3:10 AM and concluding at 9:54 AM on November 21, 1986, combined with summary evaluation of available data from before and after this period.

4

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2.

PRESSURIZER TRANSIENT EVALUATION

[

This evaluation was conducted to provide a. reasonable and timely technical basis for the determination of the acceptability of the pressurizer equipment for future operation.

Therefore, the rigorous analytical techniques normally used in the determination of a specific transient and the analysis of pressure boundary components were not used.

The analyses and evaluations performed f

to assess the metallurgical and functional condition of the pressurizer components (See Figure 1) are based on the data presented in this section.

2.1 Scone The scope of the analysis is limited to providing an assessment-of the temperature conditions for the pressurizer components listed in Table 2.

Specifically, the analytical scope is defined l-as follows:

i 1.

Establish a

sequence of events on which to base the evaluation.

l 2.

Develop a set of' compatible analytical parameters consistent with schedule constraints.

3.

Develop simplified temperature transient curves.

l l

t 4.

Analyze the pressurizer temperature history during the period from 3:10 AM to 9:54 AM.

Thermal distribution analyses of the Rancho Seco pressurizer were performed to establish transient data for use in evaluating the effects of the thermal conditions that resulted from the l

pressurizer heater incident of November 21, 1986.

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2.2 Discussion of Methodoloav Figure 2 shows a plot of the pressurizer RTD probe during the

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pressurizer heater incident (Time 3:10 AM to 9:54 AM).

Due to a lack of detailed logged data on the actual operating time of the pressurizer heaters, the RTD digital readout was used along with the control room log to determine on/off times for the heaters.

Additionally, the control room log was used to determine the l

number of heater elements and times at which they were racked out during the incident.

The on-time for the heater transient considered the time required for heatup and cooldown of the heater sheath.

i Using this data the transient shown in Figure 3 and tabulated in Table 1 was assembled.

(Note:

Figure 3 and j

Table 1 list the total heat flow for the upper bundle only).

A detailed discussion of the methodology employed to determine the pressurizer transient is presented in Reference 1.

The following assumptions were used to determine the heater bundle element activation time intervals and heat flow from the upper bundle.

These assumptions as a

whole provide a

conservative assessment of the actual transient.

(1)

The heater element requires approximately 1.5 minutes to reach 1100F (See figure of Appendix C,

Reference 1,

for predicted thermal response).

It was assumed that at this point the RTD started to digitally register a temperature change.

(2)

The RTD temperature probe records the heater element temperature instantaneously.

(3)

When the heater bundle activation stops, the temperature of the heater element drops.

It was assumed that the RTD probe temperature reading levels off at this point, since a drop in heater radiation can no longer support temperature increases while conduction distributes the metal heat throughout the pressurizer.

7

FIGURE 2 t

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O 100 200 300 400 TIME (MINUTES) i

FIGURE 3 PRESSURIZER UPPER HEATER BUNDLE ASSUMED HEAT FLOW 1.9 1.8 l

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TABLE 1

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PRESSURIZER UPPER HEATER BUNDLE HEAT FIDW DATA 1

TIME ACTIVE HEAT FIDW TIME ACTIVE HEAT FI4W t

(MIN)

GROUPS (E6 BTU /HR)

(MIN)

GROUPS E6 BTU /HR 0.00 13' l.863-246.00 7

1.003 7.00 13 1.863 249.50 7

1.003 7.00 0

0.000 249.50 0

0.000 87.00 0

0.000 257.00 0

0.000 87.00 13 1.863 257.00 7

1.003 93.50 13 1.863 258.75 7

1.003 93.50 0

0.000 258.75 0

0.000 122.00 0

0.000 269.00 0

0.000 122.00 12 1.720 269.00 7

1.003 126.25 12 1.720 281.00 7

1.003 126.25 0

0.000 281.00 0

0.000 135.00 0

0.000 302.00 0

0.000 135.00 12 1.720 302.00 7

1.003 145.25 12 1.720 308.00 7

1.003 145.25.

0 0.000 308.00 0

0.000 153.00 0

0.000 317.00 0

0.000 153.00 12 1.720 317.00 7

1.003 155.00 12 1.720 323.00 7

1.003 155.50 0

0.000 323.00 0

0.000 164.00 0

0.000 330.00 0

0.000 164.00 11 1.576 330.00 7

1.003 167.25 11 1.576 335.75 7

1.003 167.25 0

0.000 335.75 0

0.000 190.00 0

0.000 343.00 0

0.000 190.00 10 1.433 343.00 7

1.003 202.00 10 1.433 345.75 7

1.003 202.00 0

0.000 345.75 0

0.000 l

208.00 0

0.000 358.00 0

0.000 l

208.00 9

1.290 358.00 7

1.003 209.75 9

1.290 361.50 7

1.003 l

209.75 0

0.000 361.50 0

0.000 t

226.00 0

0.000 370.00 0

0.000 226.00 13 1.863 370.00 7

1.003 233.00 13 1.863 374.00 7

1.003 233.00 9

1.290 374.00 0

0.000 236.75 9

1.290 387.00 0

0.000 236.75 0

0.000 387.00 7

1.003 246.00 0

0.000 390.50 7

1.003 390.50 0

0.000 Note: Each group consists of 3 heater elements or 42 kw.

10

s (4)- It was assumed that the heaters were deactivated as soon as the RTD temperature probe reading levels off.

(5)

For consistency

purposes, the heater elements were considered to be on as soon as an RTD temperature increase is reordered.

Simarily, the heater elements were considered to be off as soon as the RTD temperature levels off.

An additional 1.5 minutes was added to each of these activation time periods to account for the initial heater element heatup delay (Assumption 2).

(6)

The middle heater bundle elements assumed to be exposed were activated during each of the upper bundle activation times.

(7)

The RTD digital readout (see Reference 1) from 8:00 AM to

-9:54 AM shows no significant heat input.

However,-the total energy input to the thermal analysis conservatively considered only the 18 elements of the upper bundle racked out (See page 40 of Reference 1) to be off during this time span.

This was considered to be very conservative; since after the incident electrical testing revealed several other elements with high resistance readings and several showing open circuits.

The pressurizer heater radiant energy distribution for the shall and upper head surface was formulated.

The formulation assumed radiation of energy from the lateral surfaces of the heater bundle.

The bundle was treated as a cylindrical heat source and the pressurizer as a black body absorber, a right circular cylinder.

Using this analogy, the calculated net heat flux on the pressurizer shell and head surfaces was calculated.

A computer program was prepared to calculate the required heat flux distribution at any point on the pressurizer inner surface.

A detailed discussion of the method and a listing of the developed computer program is presented in Reference 2.

11

..J

The pressurizer shell heat flux value calculated represerits the effect of the upper and middle heater bundles.

The heat flux value is based on a realistic but still conservative-calculation which considered the actual location of the middle bundle with respect.to the upper bundle (rotated 40 degrees) and. considered 25 percent of the middle bundle elements to be radiating heat on the shell.

This assumption of the value of participation by the middle bundle was confirmed with Rahcho Seco personnel as a result of inspections performed on the middle bundle (i.e.,

top heater element was deformed and the next four below were discolored).

In addition, no heater element electrical failures were reported for the middle heater bundle.

The calculated net heat flux (Figure 4 represents a typical distribution at the upper heater bundle centerline) was applied to the computer simulation models of the pressurizer shall and heater bundle shell opening.

The results are presented in Section 2.3.

12

4 2.3 Results Pressurizer Shell The ANSYS finite element computer code was used to perform the thermal analysis of the pressurizer shall (See Reference 3).

A 90 degree section (longitudinal symmetry was assumed) of - the pressurizer shall which included one half of the upper heater bundle was modeled (See Figure 5).

The longitudinal dimension included the RTD probe location and accounted for a portion of the water in the bottom head.

The following conservative assumptions were used in the thermal analysis of the pressurizer shell.

(1)

To provide a reasonable and timely determination of the acceptability of the pressurizer equipment, the thermal transient analysis of the pressurizer shell was performed with an assumed heat flux value.

A heat flux value equivalent to one and one-half heater bundles located at the upper heater bundle location was used.

The use of this value was shown later to be at least 30 percent higher than required (See Figure 4 or Reference 2, page 27).

(2)

To facilitate computer run

time, 30 minutes of heater element off time was deleted from the transient run and several heater element on times were added together which results in higher peak temperatures.

(3)

The cladding thickness was not in the model.

(4)

No heat loss was allowed through the outer shell insulation i

or by convection to the gas medium inside the pressurizer.

l (5)

The total volume of water in the bottom of the pressurizer was not accounted for in the model.

l The maximum localized base metal temperature determined in the l

pressurizer shell analysis was approximately 700 F.

This value 0

is approximately the design temperature (670F) of the l

pressurizer.

The maximum value was determined to be near the end 13 W

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of the upper bundle in the horizontal shell section containing

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the upper heater' bundle centerline.

The thermal results from the pressurizer shall computer model at the RTD location indicate that a conservative number of heater elements is being used in the thermal analysis.

The - computer thermal analysis predicts significantly higher temperatures at this location than were recorded by the RTD probe during the heater bundle incident.

This conservatism may be reduced when the pressurizer shell fatigue damage assessment is performed.

The effect of an individual heater element in contact with the shell was evaluated.

A conservative representation was' modeled with the ANSYS finite element computer code.

The model assumed perfect conduction between the heater tip and the shell with no heat losses to the environment.

The maximum localized increase in the shell base metal temperature was 144 F if the heater 0

element is on 30 minutes.

The shell temperature was assumed to 0

be 600 F in the analysis.

This contact temperature increase is in addition to the shell temperatures determined in the Reference 3 analysis.

However, the contact temperature increase does not coincide with the point of maximum shall temperature calculated in Reference 3.

Thus, no significant effect would have incurred if an individual heater element did contact the shell.

See Reference 6 for details of the evaluation.

Additionally, a calculation was performed to determine the load which could be developed by thermal expansion of the heater bundle elements and if these loads could cause deformation in the pressurizer wall.

The results of the calculation, Reference 8, reveal that the thermal expansion load required to buckle the pressurizer heater element does not produce sufficient force to cause deformation to the pressurizer vessel wall.

I 16

I Upper Head The results from the pressurizer shell thermal analysis show that no significant temperatures were reached by any portion of the pressurizer upper head.

Thus, no further evaluation of these areas is required.

See Reference 3 for the thermal distribution

.in detail.

Heater Bundle Shell Opening The heater bundle shell opening was analyzed using an axisymmetric thermal model (See Figure 5).

The finite element computer code ANSYS was used to calculate the thermal distribution.

The highest calculated shell heat flux values are in the horizontal plane at the hester bundle center line elevation.

These values were assumed symmetrically over the entire surface of the model.

The heat flux values used in this analysis are the calculated values shown in Figure 4 which represent the effect of 1.25 bundles.

Additionally, a

conservative heat flux value was calculated for the unheated portion of the upper bundle exposure area inside the opening in the shell.

No heat losses were allowed from the model surfaces to the environment.

Therefore, the thermal model was a

conservative representation of the actual energy being absorbed (especially at the corner node points) by the shell and remaining therein.

As a result, the calculated temperature at the inner corner of the heater bundle opening is higher than the assumed maximum shell temperature of 700 F (see page 11 for discussion of maximum shell temperature).

Figure 6 is a plot of the heater bundle opening inside corner maximum base metal temperature.

Figure 7 is a thermal contour plot of the model area at the time of maximum temperature.

The base metal temperature decreases rapidly in both directions away from the corner node point.

At a distance of 1.8 inches the maximum base metal temperature of 17

t_

0 919 F has decreased to an average temperature of 760 F, This l

0 temperature is significantly.less than the actual material qualification temperature.

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PRE 5:UPTZER HEATER BUNDLE OPENING MAXIMUM TEMPERATURE (Basemetal)

FIGURE 6 19 l

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FIGURE 7 HEATER BUNDLE OPENING'

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NOTES:

f1N = ttinimum Temperature Equals 249 F g

Contour Grid Spacing is 50 F Increments MX = tiaximum Temperature Equgls 1002 F Clad Temnerature = 1002 F c

Base Metal Temperature = 919 p 20

__--___------___---------------------------------------------------J

r.

3.

METALLURGICAL EVALUATION The effects of. temperature on pressurizer materials were assessed based on the calculated temperatures addressed in Section 2.

)

3.1 Scope This evaluation is limited to evaluating temperature effects on the properties of metallic construction materials to assess potential changes in mechanical and fracture toughness properties and corrosion resistance.

The components considered are listed in Table 2.

3.2 Results The metallurgical properties of the pressurizer pressure boundary component materials were not significantly affected by the temperatures to which they were exposed.

Table 2 lists the component materials, and the estimated temperatures to which each component was exposed.

The prese rizer was stress relieved at.

0 1100-1150 F for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> minist'm.

Ine stress relief wes performed following weld cladding and structural welding operations.

The postulated temperatures, given in Table 2,

are significantly lower than the stress relief temperature.

For this reason, these thermal exposures did not affect the metallurgical condition and the mechanical and fracture toughness properties of the base metal or cladding.

The corrosion and mechanical properties of the heater elements in the upper bundles were significantly affected; however, they have been replaced.

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3.3' Discussion The metallurgical condition of the pressurizer components as presented in Table 2 depends on two primary considerations - (1) the temperature range and/or the peak temperature the material experienced, and (2) the length of time of exposure.

The assessment of material condition was based on the conservative estimate of the thermal exposure.

Since, the ASME code has no i

specific guidelines for requalification of a pressure vessel that has been subjected to a transient condition above its design temperature, the following methodology was employed.

In general,.

it was assumed that if the temperature the material experienced during the incident was not higher than the fabrication temperatures and that the time of exposure was not excessive, the material did not suffer metallurgical degradation (e.g.,

pressurizer carbon steel components are stress-relieved at 1100-0 1150 F for approximately 5-10 hours followed by furnace cooling 0

at about.15 F/h).

The interior surfaces of the pressurizer near the heater bundle shell opening corner are manually clad with stainless steel.

The I

first layer is Type 309 and the. second layer is Type 308.

The pressurizer stress relief is performed after welding and weld cladding.

"'he cladding has a microstructure that includes small amounts of delta-ferrite that makes it virtually immune to stress corrosion cracking (SCC) following the stress relief heat treatments.

The postulated thermal exposure resulting from the heater bundle temperature excursion is therefore ir=ignificant with respect to SCC respectively.

l l

Although there is some uncertainty in actual temperature, it is realistic to expect that based on the conservative estimate of probable temperature, the pressurizer pressure boundary component parts should not have been degraded as a result of the transient.

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Table 2.

' Pressurizer Materials, Thermal Exposure and Damage Assessment Est Incident Probable temp, F/ time metallurgical Component Material at temo damace?

Pressurizer-SA516, GR-70 700/0.5 Hrs No Shell Heater Bundle SA508, CL-1 919(a)/0.5 Hrs No opening Inside Corner Heater. Sheath SA213, TY316L 2000(D)

Yes Cladding at Type 309 & 308 1000(c)/0.5 HRS No Heater Bundle Opening Corner (a)

Localized value at corner of heater bundle shell opening (see page 15 for discussion)

(b)

Sensitization temperature range is 800-1600 F.

0 (c)

See page 20 for discussion of process.

23

s.

l l

6.

REFERENCES 1.

B&W Document No. 51-1167607-00, " Heater Element Activation Time Intervals", Rancho Seco.

2.

B&W Document No. 32-1167978-00, "SMUD Pressurizer Heater Radiant Energy Dictribution", Rancho Seco.

3.

B&W Document No. 32-1167603-00, " Pressurizer Shell Temperature Due to Radiant Heating", Rancho Seco.

4.

B&W Document No. 32-1167974-00, " Local Heating Pressurizer Shell Inside Corner", Rancho Seco.

5.

B&W Document No. 32-1167609-00, " Heater Element Temperature at Closure Region", Rancho Seco.

6.

B&W Document No. 32-1167984-00, " Pressurizer Ccntact Temperature with Heater Element", Rancho Seco.

7.

" Pressurizer Stress Report", B&W NPD Microfilm Roll No. 80-47, Rancho Seco.

8.

B&W Document No. 32-1167616-00, " Pressurizer Heater Element Punch Load", Rancho Seco.

24

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ENGINEERING INFORMATION RECORD Document Identifier 51 1167607-00 Title heater Element Activation Time Intervals PREPARED BY:

REVIEWED BY:

Name Peter W. Ploch Name C. W. Tally Signature

/

/M Date l!'f!Y7 Signature O-Date 2,1 Sf 8 7

( pl V // u Technical Manager Statement Initial i/l9/9%

Reviewer is Independent.

Remarks:

The intent of this Engineering Information Record is to document the data and procedure used to determine the time intervals and number of heater elements activated during pressurizer bundle heating in a steam environment.

Page 1 of 56

D0C. I.D. 51-1167607

. w s

4 The digital pressurizer temperature data (Attachrent A) was reviewed to determine the time intervals during which the heaters were energized. A comparison with the control room log was not conclusive in determining the heater energization time interval length nor does the logged number of activations correspond to the total number of digital temperature peaks.

Therefore, the digital temperature data was used exclusively to determine the time dependent off/on sequence of the heaters.

The control room log (Attachrent B) was used to acccunt for the non-energization of Bank 2 after the 03:14 peak and the timing of the racked out/in of bundle elements.

A certain element of uncertainty is involved in the precise determination of the switching time of the heaters. This difficulty is due to the lag in the thermal response of the heater element (Attachment C). From the predicted I

thermal response, it was deduced that it would take 1 to 11 minutes before the pressurizer temperature probe would record a higher temperature due to the-energization of-the heater bundles and that this temperature would decrease as soon as the heater temperature decreased. Thus, the heater "on" time span was determined to be the time interval between the first indication of a temperature rise to the time at which the probe temperature ceased to increase. Since all the energy from the heater elements has to be accounted for, the li minute time lag was added to the time interval derived exclusively i

from the temperature changes. Please see Attachrent D.

l Prepared by Peter W. Ploch Page No. 2

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D0C. I.D. 51-1167607 Bundle Energization/Non-Elements x3 Energization Time Calculation-Heat Flow Out Interval (Min)

Time (Min)

Btu /h 0

6 0

7 7

2.723x10 80 87 0

6 0

61 93b 2.723x10 28-3/4 122k 0

6 1

41 126 2.580x10 9k 135-3/4 0

6 1

101 146 2.580x10 7-3/4 15 3-3/4 0

6 1

21 156k 2.580x10 8

164%

0 6

2 31 167 2.436x10 23k 190-3/4 0

6 3

12 202-3/4 2.293x10 6k 209 0

6 4

1-3/4 210-3/4 2.150x10 l

l 16-3/4 227 0

6 0

7 238k 2.723x10 6

i 4

3-3/4 2.150x10 9-3/4 248 0

l 6

6 31 251b 1.8623x10 7

258 0

6 6

1-3/4 260k 1.8623x10 Prepared by Peter W. Ploch Page No. 3

00C. I.D. 51-1167607.

~

10-3/4 271 0

6 283 1.8623x10 6

20 303h 0

6 6

6 309 1.8623x10 94 319 0

6 6

6 325.

1.8623x10 7k 332k 0

6 6

5-3/4 338 1.8623x10 7

345 0

6 6

2-3/4 347-3/4 1.8623x10 12 359-3/4 0

6 6

3S 363k 1.8623x10 10 373h 0

6 6

4 377k 1.8623x10 0

12 389-3/4 6

6 3

393%

1.8623x10 The number of elements racked out are based on the last entry of control room log and may change if new data becomes available.

Each rack out involves $tgJements; the hegt flow is calculated as follows:

14 KW x 3 x 3.4121 h/w = 1.433x10 Btu /hr l

Prepared by Peter W. Ploch Page No.4

[ t - 1 L L ~l G o ~7 o

O D

ATTACHMENT A m

e

.- l

y - u s en PRESSURIZER Hm.ATER EVENT TEMPERATURE COMPARED WTill IJtVEL q

d MGOt2 d.

.4 e G 4 4: F.&

g we

p. y FF l

l n20 --

ArsA

+

.]-}

200 -

i geC k

• * '8 go 100 -

o

.4

-i k

ll 1

"""gM*

C.9 T l

W m

160 O

TEMPFJ A1URE

~ ~ -.

S. 4 f' T

.U w

u hh 140 -

l 3,-

w d

Q U 120 -

(N g

100 -

s 6

J 00 -

g GO -

T..

E..

b l

e 2*

40 -

^

IIVEL (O ANNEL B)

Q no -

I O ^^^ -

d 0-

=U

-20

= = = = = = =

4 250 4in 630 650 810 930 1050 i

T Tinne 2

il il %

r FIGURE I

-J e

f

.J S- - _ - _ __ -

~

PRESSURIZER. HEATER EVENT TEMPEltATURE COMPAREN WI'11I IEVEL P,4 0 -'

13P,0 -

\\,

. oo -

I

{

suo -

L 1" itia -

TINI'El NIURE f

(

v f'40-h

)

2 i :o m

100 -

T i

00 -

Liu -

4U -

1.EVEL (d ANNIU,11) h

o n

[h LM A4

-^

g u.

u

.-::o

• .5o 810 530 G50 810 930 1050

t i

Tianc c

FIGIIRE I J

c ti 8

d J

3 o3

-c 4 v. ~. -

ALOMANUMERIC TREND DRIN7007 pot twe> paE ff - I I (, ~7 L, o*1 G'a c

!I!;iI ESC #I'7*0N: ! 133 W31Z IE.iW2 2Li.*!'.*2CdE.....

SA*PLE

• ATE:

" TEMP LEVEL A t.EVEL B LEVEL C, FitE5N1tC 7009 LOO 5 L009 LC10 8034 3

1 - - -

1,- - - - - -

1 3. - - - - - -. I. - -....

• 1 1....,

'II.-

I-21 l 3:13:30 79.73 168.8 307.E 307.5

.72 11/21/ 16)03:13: 45 79.73 168.8 307.8 307.5 3.72

[ 11 /21/ 16T 03: 14: 00 79.73 168.8 307.8 307.5 33.72 11 /21/ J5 103:14: 15 77.73 168.8 307.8 307.5 33.72 11/21/ 5 03:14:30 79.73 169.3 307.8 303.6 33.72 4

11/21/ 36 03:14: 45 79.73 169.5 307.5 308.6 33.'2 l

11/21/ 86 '03:15:00 79.73 169.5 302.3 303.6 33.*'

h11/21/ 2. 03:15:15 79.73 169.8 309.3 302.6

33. 5 11/21/ 56 03: 15:30 79.73 171.9 310.3 310.5 33.72 i

( 11/21/ t6 '03: 15:45 79.73 171.9 310.3 310.5 33.??

) 11/21/ Sd 03:16:00 83.57 173.o 312.1 312.2 33.72 11/21/ 56 03:16:15 83.57 173.6 312.1 312.

33.72 11 /21) 85)03:16:30 93.57 175.7 314.1 314 33.72 11/214 56 03:16:45 58.62 175.7 314.1 314 3 33.72 11/21J !6 03:17: 00 88.62 177.8 316.4 31

.3 33.72 11/21 ' 9 e1 03:17:15 93.87 177.5 316.4 31

.3 33.72 i

11/21 rS6 03:17:30 93.87 1'9.9 31!.5 3 3.~

47.21 11/21/ 66' 03: 17:45 100.1 174.9 315.5 18.4 47.31 11/21/ 86 l03: 18:00 104.1 182.2 320.5 20.7 47.31 11/21/ 2. 03:18:15 104.1 132.2 320.8 320.7 47.31 11 /21 / !6 03:18:30 111.4 124.4 322.9 322.7 47.31 11/2' /!

03:15: 45 115.3 154.4 322.9 322.7 47.31

'2' /56 03:19:00 119.1 156.3 324.7 324.5 47.31 2 l/36 103:19:13 123.1 156.3 324.7 324.5

.7.3i 1/56 30 123.1 157.3 325.6 324.5 47.31 1/56{03:19:

../2 03: 19:45 129.2 187.3 325.6 324.5 47.31 11/2 11/c1/E6 03:20:00 129.2 157.3 325.6 324.5

.7.31 Ig 134 4 187.3 325.

324.5 47.31 11/ 21/3. 03:20:15 134.4 187.3 325.

324.5 47.31 11/ :1/ic 03:20:30 g4h 138.5 187.3 325 6 324.5 4?.31 (11/ 11/i 03:20: 45 137.3 325.6 334.5 47.31

[11/ !1/36 03:21:00 dll138.5 138.5 157.3 32.6 324.5 47.31 /

,1 * / 21/56 03:21:15 11/ 21/i6' 03:21:30 142.6 185.6 3 50.

I24.5 47.3 * /

%(f)142.6

) *1/ 21/YA 03:21:45 135.o 363.6 324.5 47.31 f

11/ 21/!e'03:22:00 142.6 155.6 23.6 322.9 47.31 11/ 21/66 03:22:15 142.6 135.6 323.6 322.9 47.31

11. 21/56 03:22:30 142.6 134.1 322.5 322.9 47.31 I

11 21/is 03:22: 45 142.6 154.1 322.5 322.0 47.31 j l

11 '21/Sg03:23:00 dummer142. 6 154.1 322.5 321.6 47.11 03:23:15 142.6 134.1 322.5 321.6 47.31 11 '21/26 11 /21/!6 03:23:30 142.6 152.7 321.3 321.6 47.31

( 1* /21/id03:23: 45

_142.6, 152.7 321.3 321.c 47.31 11 f

/21/ 6 03:24:00 142.6 182.7 320.3 320.6 47.!*

11 /21/5th03:24: 15 142.6 132.7 320.3 32C.e 47.31 15 /2'/36 103:24:30 142.6 1B1.

320.3 320.6 47.31

/21/Sq03:24: 45 142.5 131.

320.3 320.6 47.31 11 1' /21/it 03:25:00 ",

142.6 131 6 310.0 319.1 4'.31

/21/!t 03:25:15 136.7 121.4 319.0 318.1 7.31 d

21/16 03:25:30 135.7 13.2 311.0 319.1 47.31

.-/.21/ ! 6 ' 0 3 : 2 5 : 4 5 132.7 1 0.2 318.0 119.1

.31 l

1 1/I1/36 03:26:00 135.7 1AC.2 317.0 313.0 7.31 ii/21/54 03:26:15

& 13E.7 180.2 31'.9 3*i.0 7.31 j

71/21/!: 03:26:30 134.6 119.1 31'.'

315.0 47.3' 11/21/1 03:26:45 134 6 179.1 31 7.9

!15.0 47.31 Q

7 g a,h-[-> ('a y-)

tver-

~

u ALCHANu9ERIC 7 REND PRIN70UT

\\

-tsa

c. e 3RCUP: 21121I DESCR:PT:tN. !!!11W!I;i!.5W52ki :iLI22nh.....

SAFPLE RA7E't. ;,

[a 7009 LOCS LC09 LO10

1. C34 f.,.!!

....II!!....

259.1....

1S.......

15.......

.IN.......

.!1;G...L..!

k B6 O3:27:00 134.6 179.1 316.9 316.6 47 3' 4

11 /21/

11/21/ !f 03:27:15 134 6 I179.1 316.9 316.6 47.31 4

I 11/21/ 96 03:27:30 131.1 179.1 316.9 315.4 4.31

/

4 11/21/ 56 3:27: 45 131.1 179.1 316.9 3t!.c

.3:

i a

11/21/ 36 03:28:00 131.1 177.8 316.C 315.4 7.3t 5

11/21/ 86 03:23:15 131.1 177.8 316.0 315.4 47.3-e 11/21s 86 3:25:30 127.2 177.8 316.0 315.4 47.2 i

11/21J 86 03:23: 45 127.2 177.8 316.0 315.4 47.3-11 /21 ' S6 03:29:00 127.2 1

177.5 316.0 315.4 47.!-

11/21

36 03:29:15 127.2 1 177.2 316.0 315.4 47.I-e 11 /21 If 23:29:30 122.0 176.e 314.5 315.4 47.3-e 11/21 86 03:29:45 122.9 j 176 6 314.8 315.4 47.3-6 11/21 sc 03:30:00 122.0 176.s 314.8 315.4 47.3*

11/2 /56 03:30: 15 122.9 17o.6 314.8 315.4 4'.3*

e 11/2'/16 03:30:30 11c.3 176.6 314.5 314.s 47.:-

119 3 17e.6 314.8 314.4 47.2-i/36[03:30:45 11/2 1/56 03:31: 00 119.3 175.o 313.7 314.4

.7.2-11/2 j11/2 1/36\\03:31:15 119.3 175.6 313.7 314 47.39 l

- 11/2 1/56 3:31:30 115.6 175.e 313.7 314 47.3i 11/2 1/36 03:31: 45 115.6 175.6 313.7 316 4 47.3' 11/2 1/26 03:32:00 115.6 175.:

313.7 I13 3 47.31 11/21/B6 03:32:15 115.6 175.e 313.7 31.3 47.31 e

1/86 03:32:30 115.6 175.o 313.7 31.3 47.31 e

. 1/5 03:32: 45 112.0 175.6 313.7 3 3.3*

47.31 11/11/5 C3:33:00 4 112.0 174.5 313.7 3.3 47.31 11/i!1/5 03:33:15 w 112.0 174.5 313.7 13.3 47.31 11/ 11/56 03:33:30 112.0 174 5 313.7 313.3 47.31 11/ !1/66 03:33:45 112.0 174.5 313.7 313.3 47.31 11/ 21/25 03:34:00 108.3 174.5 312.4 313.3 47.31 3

11/ 21/56: 03:34:15 106.3 174.5 312.4 313.3 47.31 0

11/ 21/if 03:34: 30 108.3 174.5 312.4 312.3 47.31 3

1 11(21/3e 03:34:45 108.3 174.5 312.4 312.3 47.31 I

117 21/ 56k 03:35:00 %

~

174.5 312.4 312.3 s'.31 108.3

/

• 1 /I1/56 03:35:15

-105.3 174.5 312.4 312.3 47.31 11 /21/26 03:35:30 108.3 174.5 312.4 312.3 47.31

?

4l11 /21/86 03:33: 45 104.7 174.5 312.

312.3 47.31 I

11 /21/36 03:36: 00 104.7 1'e.5 312/4 312.3 47.31 ~/

11 /21/56 03:36:15 104.7 174.5 31 7.4 312.3-47.31 11 /21 /16 03:36:30 104.7 173.2 3

4 312.3 47.31 l

1' /21/if 33:36: 45 10&.7 1'3.2 2.4 312.3 47.31 e

1' /21/Bo 03:37:00 104.7 173.2

.11.2 312.3 47.31 I

\\1 ! / 21/ i s 03:37:15 104.7 173.1 311.2 312.3 47.31

!1 1/21/56 03:37:30 104.7 173.2 311.2 312.3 47.31

/

1 */21/te 03:37: 45 104.7 173.2 311.2 312.3 47.31 1 1/21/56 03:31:00 101.1 173.2 311.2 312.3 47.31 311.2 312.3 47.31 1 1/21/!6 C3:38:15 101.1 173.2

/1 1/21/56 c03:38: 30 101.1 173.2 311.2 312.3 47.31

'1/3e 03:38: 45 101.1 1'3.2 311.2 312.3 47.31 I

i1/ ti j 03 :39 :00 101.1 1'3.-

31*.2 311.1 4'.3*

1/21/26 03:39: 15 101.-1 1'3 t 311.2 311.1 e7.31

\\g 173'2 311.2 311.1 47.31 2

1/21/56 03:39: 30 101.1 1.1/ 21/ E e 03:39: 45

• 01.1 17.2 311.2 311.1 47.31 3

1C1.1

3.I 3*1.2

?11.1 45.

1

)11/21/io03:40:00 11/21/ Ep 03:40:15 101.1 (1/3.2 311.2 311.1 47.31

~

O

a s nLO h(vfit (4 bl&

AL*HANUMERIC TREND PRINTOUT hI D :/

• 3 g } } h 31111.3 g g g g g.g g (I g g g g.....

3 AMBLE RATE li GROJ8: EIB2AI DESCR!* TION.

T009 LOO 8 LOO 9 LC10 PC34 o

....II.

.....I151....

21G.1....

15.......

.!3.......

15.......

.!1;2....

.i 11/21/3 03: 40:30 101.1 173.2 311 2 311.1 47.31 11/21/86 03:40: 45 101.1 173.2 311.2 311.1 47.31 2

11/21/86 03:41: 00 101.1 173.2 311.2 311.1 47.3 1

11/21/56 03:41:15 96.58 173.2 311.2 311.1

.7.13 3

11/21/86 03: 41:30 96.58 171.9 311.2 311.1

47. 1 3

11/21/86 03:41: 45 96.58 171.9 311.2 311.1 47 3-3 11/21/3d 03:42:00 96.58 171.0 311.2 311.1 47.3.

I 11/21/50 03: 42:15 96.58 171.0 311.2 311.1 4.31 3

11/21/ad03:42:30 96.58 171.9 311.2 311.1

.3*

3 11/21/!a 03:42:45 96.58 171.9 311.2 311.1 7.3*

I 11/21/3 > 03: 43:00 96.55 171.9 311.2 311.1 47.31 3

11 /21 /5 b 03: 43:15 96.58 171.9 311.2 311.1 47.I' 3

11/21/2 5 03:43:30 96.58 171.9 310.2 311.1 47.3-11/21/i s 03:43 45 96.56 171.9 310.2 311.1 47.3' 3

11/21/3 6 03:44: 30 96.55 171.9 310.2 311.1 47.I' 3

11 /21/? f 23: 44: 15 96.58 171.9 313.2 311.1 4?.3-11/21/i s 03:44:30 96.58 171.9 310.2 311.1 e7.3*

3 I

f 11/ 21/.: 6 03: 44: 45 96.58 171.9 21

.2 311.1 47.31 11/21/L : C3: 45:00 96.59 171.9 310.2 311.1 67.3-l 11/21/ 9[03: 45:15 9b.58 171.0 310.2 311.1 47.31 3

11/21/.6 03: 45:30 96.58 171.0 310.2 311.

47.31

?-

11'21/5: 03: 45:45 A' 96.58 1 71.9 310.2 311.

~~.31 1 36 03:46:00 ld 96.58 171.9 310.2 311 1 17.3' 3

1 56 03:46: 15 96.58 1'1.9 310.2 31

.1 e7.31 3

11 /21 56 03: 46: 30 96.58 171.9 310.2 3 1.1 47.31 l

1*/2"/55 03:46:45 96.58 171.9 31C.2 3 1.1 47.31 11/2 /ie 03: 47:00 9e.58 171.9 310.2 11.1

.7.31 11/2 /S.6 03:47:15 92.35 171.9 310.2 311.1 47.31 3

11 /2 I:- 03:47: 30 92.35 1 71.9 31C.2 311.1 47.31 11/31/16 03:47: 45 92.33 171.9 310.2 311.1 47.31 11/ 1/it C3:48:00 92-.35 171.9 310.2 311.1 47.31 11/ 1/5e 03: 48: 15 92.35 171.9 310.2 311.1 47.3* k 11/ 1/i: 03:46:30 92 35 171.9

'10.2 311.1 47.31 x

j 11/ 41/ 5 d 0 3: /J6: 45 92.35 171.0 310.2 311.1 4'.31 j

{ 11/21/50 03: 49:00 92.35 171.9 31*.'

309.9 7.31 11s21/!" 03: 49:15 92.35 171.9 310.

309.9 47.31 2

171.9 31 2

3 3.9 67.31 45I)ll92.35 1*

2*/!

03:49:30 92.35 171.8 31.2 309.0 47.3'

~

11 '21/5 03: 49:

11 '2*/!$ 03:50:00 92.35 171.9 3 s.2 309.0 47.21 11 /21/1s,03:50:15 92.35 171.9 0.2 303.9 47.31 11/21/E: Jol: 50:30 92.35 171.9 10.2 308.9 47.31

. 9.9

.7.31

~

/ 2.1/ i 6[ C 3 : 5 0 : 45 92.35 1'1. 9 310.2 1 /21/it 03:51:00 92.35 171.9 310.2 3: 9.9 67.31 1 /21/it 03:51:1F 92.35 171.9 310.2 309.9

47. 31 1 /21/1e 03:51:50 92.35 171.9 310.2 309.9 47.31 310.2 308.8 47.31 j

11/ 21/ ! c 03 :51 : 4 5 86.77 171.9 1/29/!6 03:52:00 88.77 171.9 310.2 209.2 7.31

'1/36 03:52: 15 88.77 171.9 310.2 309.3 47.31 1/56 03:52:30 88.77 171.9 313.2 309.5

.7.31 11/21/26 03:52:45 68.77 171 310.2 3:9.3 e7.31 k

11/21/i: 03:55:00 88.77 171 :

310.2 3:4.9 47.31 11/21/5:

03:53: 15 88.77 17 4

51

.2 3:?.;

4.31 11 88.77

, 1 71.9 31:.2 339.8 47.31 (g/21/se03:53:30

/21/!: 03:55: 45 88.77 31 20.9.9 7.31 l

y

(M r.e CLLA ' M

'Qgrp' V R -p-gi - u c s w ALPMANUF.!UC TREND PRINTOUT 3:0ue: gI!21I Dista:PTION:

111W31][1 !'J3;Li.*jLIE;f 3.....

SA*PLE,oaTik ;,

/

T009 LOO 9 LC13 003*

...il J.....::55....

212.t..k. LOO 8: 3........ a........ : s........ e yJ...

i N

/.3:

11/ 21/ a f 03:54:00 48.77 171.9 309.0 309.9 7

i 11/31/3 d 03:54:15 88.77 171.9 309.0 3C9.9 47.3' l

11/21/i 6 03:54:30 88.77 171.9 300.0 309.9 47.3*

11 /21/2 6 03:54:45 88.77 171.9 300.0 309.9 47.!-

11/21/! 6 03:55:03 88.77 171.9 309.C 300.9 47.2-11/21/5 et03:55: 15 88.77 171.9

!32.0 339.9 47.:'

11/21/9 6' C3:55:30 88.77 171.9 309.0 309.9 47.2*

11/21/i6 03:55: 45 88.77 171.9 309.

309.9 s'.!*

I 11/21/d6 03:56:03 88.77 171.9 309.0 309.9

'7.!*

[ 11/21/d6 03:F6:15 68.77 171.9 309.0 3:9 7.:'

11/21/d6 C3:56: 30 88.77 171.9 309.0 309 6 7.!*

11/21/$6 03:56:45 88.77 171.9 309.C 309 9

'7.!-

{

11/ 21/($

i 03:57:00 88.77

/171.9 30e.0 30

.9 47.I*

11/21/56 03:57: 15 88.77 f 171.9 309.0 3

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11/21/ 6 03:57:30 88.77 171.9 309.3 3J9.9

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11/ 21/.; 33:57: 45 86.77 171.9 309.3 709.9 47.I*

11/21/56 23:58:00 88.77 171.9 339.0 09.9 4 7. ! * -

11/21 36 03:58:15 68.77 171.9 339.0 309.8 47.3*

11/21s sc 03:58:30 88.77 171.9 339.0 308.9 47.3*

11/21 '56 33:58:45 88.77

' 171.9 339.3 339.9 e'.3*

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11/2' J36 03:59:00 88.77 171.9 309.0 308.9 47.3' N

• 21 'E6 03:59:15 88.77 171.9 339.0 309.9 47.3*

h 86.77 171.9 309.0 309.4 47.3 * ;

.'!$ 03:59:30 J!i 33:54:45 88.77 171.9 304.3 309.9 47.3i 3

{1*'2* 'Ifjo4:00:00 88.77 171.9 309.3 309.9 47.31 i

• 1/:'

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304.9 47.31 l

j 1* :-

'!t 04:33:30 88.77 171.9 309 309.9 4'.3*

!$ 04:00: 45 88.77 171.9 309.

339.9 47.31 f

4 04:01:00 88.77 171.9 300 0 309.9 47.31 i: 04:01:15 88.77 171.9 30.0 339.8 47.3*

{34: 01:30 88.77 1'1.9 3 0A.0 309.9 32.31!

34:01:45 83.77 171.9 309.0 3:9.9 32.11:

04: 02:03 98.77 1'1.9 50.0 309.9

32. 31 1'

04:02: 15 88.77 171.9

.39.

309.9 32.21 k.

g04: 02:33 88.77

' 171.9 309.0 339.9 32.31

.: l34: 02:45 88.77 171.9 30*.0 309.9 32.i'

. *f 34:03:00 86.77 171.9 339.0 309.9 32.21 j

04: 03:15 88.77 171.9 339.0 339.9 32.51 1*

04: 03:30 98.77 171.9 309.0 309.9 32.31 1

.: ' 4: 03:45 88.77 171.9 308.0 J03.9 32.!1 i

I

.:t04:04:00 88.7?

171.5 3 0 9. ~,

309.9 32.51 j

. :l 34:34:15 88.77 171.9 108.0 309.9 22.s1 g

04:04:30 88.77 171.9 304.0 339.9 32.!1 l

4 1*

04:04: 45 88.77 171.

3C9.*

309.9 32.31 C4:05:30 88.77 1'O 309.0 309.9 32.!1 t

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305.8 II.fi

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335.5 33.i' I /*: 04:06:00 88.77 1

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04:06:I5 88.77

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• /21/it 04:06:30.

88.77 70.7 330.0 339.9 3 2. !*

j 1/21/ : 04:06:45 88.77 k

170.7

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3'*: 1 ii/21/i 04: 07:00 88.77 173.7 308.2 309.8 3E.31 11/:1l',04:07:15' 88.77 170.7 3~*.'

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' ^E47 ALPH&NuwEDIC TREND PRIN7Cdf

-[04bl J b h R

f(-tIL7(.o7 23 E 33 U l * ! ii.I U 5 2 k l.5 s L I2776..'.fsf8 A 7 E :

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laCJP: E!32i.

DE3C' P7~0Ni

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11/21/86 04: 07:30 88.77 170.7 300.0 309.9 32.51 11/21/86 04:07: 45 88.77 170.7 309.0 309.9 12.!

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81 - t l L 7 L o *7 e e D ATTACHMENT B 7C

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TELECOP!!R TRANSMI**AL COVER SHEET DATE: / 2 /. F7 _ ru!: /g /t PLEASE DELIVER THE FOLLOWING PAGES 70: NAME: C HARLEs TA L L V e ZFFT FIRM: d(V CITY: LVNC48URG, 1/ A TELECOPY NO.: R 084 % P f.3331_ VERIFY NO.: THIS TELECOPY SENT BY: NAME: T*o m F' A tr a t r EXT: utru ARg4 No.:

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i PRESSURIZER HEATER EVENT ~ TEMPERATIJRE COMPAP.EII Wi11I IEVEI. i 040 - 1 i enn - \\< 1 coo - 9 I f. t uu -- I h l h g*gh - j L ItM*D A111RE ( m ) M I 40 - Ii ) ] r4 j @snu g-1 m i i " sou - s i j. DO - I l su - 1 i in - ^ 1.EVP.I. (G 4880iFJ. II) I z Up - [ [b \\_ _ m N O a-^ e a- "J ~ .:n - 250 410 530 650 810 U30 1050 2 l Tistne ~_ FICl!RF. I C i i e h io

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o.....a Babcock &Wilcox f, 7 ',, " ,,,..........,,, c.,,,,,,,......oe, m m g, k w w To I r/ W. J. OBERJOHN - STEAM GENERATOR TECHNOLOGY SECTION From R. A. KUCHNER - REACTOR TECHNOLOGY SECTION Cust. "'.tof.TS-0VT-77 j slle6088-01 i er Subj* Oste THERMAL RESPONSES OF PRESSURIZER HEATER ARE PREDICTED MAY 5, 1978 g._. -. ~ INTRODUCTION B&W's contract with Consumers Power Company to furnish a nuclear steam supply system (NSSS) requires that the life of the intended pressurizer heaters be demonstrated. The heater manufacturer, Wiegand Company, performed an accelerated life test of the heaters which indicated that the required life would not be achieved. In that test, the power (14 KW) to the heaters was repeatedly cycled on and off while the heater was exposed to a room air environ-ment. Considering the differences between those test conditions and the NSSS pressurizer conditions, NPGD requested that Steam Generator Technology perform an accelerated life test under more realistic conditions. The in-house life test will consist of imersirig three heaters in saturated water at 2200 psi, applying power to the heaters repeatedly in an on/off cycle, and recordir.g the number of cycles until failure or until reaching the number of cycles required by the contract. The applied power will be 17.5 KW,125 per-cent of rated power. The minimum duration of the heating and cooling processes was specified by NPGD as: power on for one minute and power off for two minutes. The duration of these cycles must be long enough to insure that the heaters reach the steady-state temperature distributions associated with both the power-on and power-off conditions, while minimizing the total time required for testing. The following paragraphs discuss the objectives, results and recortmendations, and the analysis for this investigation, cc: J. S. Gellerstedt F. C. Kulieke C. W. Pryor - NPGD, Lynchburg R. M. Reyns - NPGD, Lynchburg H. W. Wahle At

fl-li b 7 L o 7 Babcocks,Wilcox W. J. Ober.iohn May 5. 1978 OBJECTIVES The objectives of this investigation were to: e assess the adequacy of the minimum heating z,d cooling cycles specified by NPGD for the in-house life test e provide predictions of the thermal response of an NSSS pressurizer heater during both the in-house and Wiegand life tests. RESULTS AND RECOP99ENDATIONS The results of this investigation are: e The thermal response of the pressurizer heater for the in-house test conditions was predicted. The heater will reach an approximate steady-state temperature distribution (to within 20.5 F) for either the heating or cooling process within one-half minute after the step change in heat input. e The thermal response of the pressurizer heater during the Wiegard life test was predicted. The temperature distribution within the heater under these test conditions is considerably different from those encountered in the NSSS pressurizer. I reconnend that the minimum heating and cooling cycle times (one and two minutes respectively) specified by NPGD be used for the in-house life test of the pressurizer heater. ANALYSIS General A general two-dimensional, transient conduction heat transfer model of the pressurizer heater was developed using the TRUND(1) programs. Figure 1 exhibits the general thermal model*. This general model was used to perform three simulations: e Model Verification Test e In-House Life Test e Wiegand Life Test The physical dimensions and material specifications needed to develop the general model were obtained from an assembly drawing of the heater l2) and from measurements of a similar heater which was dissected.

• Symbols are defined at the end of this report.

47

J t - L i t. ') L o 7 Batock&Wilcox W. J. Oberjohn May 5, 1978 General Model Verification A simple laboratory experiment was used to verify the accuracy of the general heater model. The experiment involved suspending a painted heater in still room air, applying a small amount of power (111 watts), and recording the temperature response of the outside surface at various locations. The heater was coated with a paint of high and known emittance to enhance radiation heat transfer which is more predictable than natural convection heat transfer. Figure 1 and Table I completely describe the spatial representation, thermophysical properties, heat generation rates, boundary conditions, and initial conditions used to model the verification experiment. Figures 2 and 3 exhibit the thermal responses measured during the i laboratory experiment and the predictions from the analytical model. _ These favorable comparisons demonstrate the adequacy of the general heater model. Simulation of In-House Life Test The model used to predict the thermal response of the pressurizer heater during the in-house life test conditions is completely described by Figure 'I and Table 2. Because this test will be conducted in near saturated water, the convective coefficient could not be predicted with a high degree of confidence. To cover the possible range, two simulations wem run with diffemnt convective 2 film coefficients. Thefirstcoefficientof10,800 Btu /(hr-ft-F)forthe A second coefficient of one-half that calculated (5,400 Btu /(hr-ftgorrela heater region was calculated based on Rohsenow's nucleate boiling -F)was also used to cover the low end of the range. These predictions are termed cases 1 and 2 respectively. l . The different_ convection coefficients did not significantly affect the temporal response (time constant), but did affect the magnitude of the change in temperature throughout the region. The results for both cases are shown in Figures 4 through 7. The-figures show that both the heating and cooling cycles will achieve a near steady state value (to within 0.5 F) in approximately l one-half minute. Simulation of Wiegand Life Test l The model used to predict the themal response of the pressurizer heater during the high power air tests conducted by Wiegand is completely des.cribed by Figure 1 and Table 3. The simulation of the heating process was teminated l at fifteen minutes and the resulting temperature distribution was used as the initial conditions for the cooling process. This is consistent with the Wiegand test procedure. Forced convection was used for the cooling cycle in the Wiegand tests but the air velocity is unknown. The simulation assumed natural convection which provides a worst or limiting case. Forced convection would augment the cooling and reduce the time required for the heater to cool to a'unifom ambient temperature. A O a

at-stu / t. c 7 i Babcock &Wilcox W. J. Oberjohn May 5, 1978 The predicted thermal response of the heater subject to the Wiegand test conditions is depicted in Figure 8. P b \\ \\ \\ 'N%( Af - L'A' 8

• ___

R. A. Kuchner RAX/llb Attachment 2 e A C

a ( - l l ta l to ol o e THERH0 PHYSICAL PROPERTIES Thermal Conductivity, Specific Heat,

Density, Temp.

K Region (Camposition) F Btu /(hr-ft-F) Btu /(pIb,-F) lb,/ft C o Sheath (316SS) 70 8. 0.11 498. 750 11. 0.13 498. 2200 17.5 0.18 498. Insulation (Hg0) 70 23. 0.25-224. 750 9. 0.29 224. 2200 4. 0.32 224. Inner Heater (Micr + Mg0) 70 10. 0.15 421. 750 10. 0.18 421. 2200 11. 0.22 421. Outer Heater (Nitr + Mg0) 70 11. 0.17 393. 750 10. 0.20 393. 2200 10. 0.23 393. Lead Wire (Ni + Mg0) 70 24 0.24 250. 750 11. 0.28 250. 1500 7. 0.29 250. TOTAL HEAT INPUT AND HEAT GENE' RATION RATES Total Heat Input: 14.0 KW/ full 80-inch length of heater Heat Generation ~ Rates: 6 3 Inner Heater: 21.01 x 10 Stu/(hr-ft) 6 3 Outer Heater: 75.52 x 10 Btu /(hr-ft ) 6 3 Lead Wire: 0.315 x 10 Btu /(hr-ft ) BOUNDARY CONDITIONS Ambient Temperature: 70 F Surface Heat Transfer Coefficients: =.19 (7 -T,)0.33 Btu /(hr-ft,7) Convection h 2 c 3 4 4 T -T Radiation h * ** r T where: e = 0.85 (oxidized stainless steel) INITIAL CONDITIONS Heating Pug.ess: 70F(uniform) Cooling Process: Heating process temperature distribution at t = 15 minutes TABLE 3. THERMAL CONDITIONS FOR SIMULATION OF WIEGAND TEST r

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f t - I L L ~) b=7 C O G ? e e ATTACHMENT D 1 1 l e 6 ~ ~ - - ~ - - ~ ~.- -

[ ( - ((1. 7 b o 's o Heater Activation Time Interval Calculation Assumptions (1) The temperature probe records the heater temperature instantaneously. (2) It takes the heater about 11 minutes to reach 1100*F (Please see figure of App C, for predicted thermal response). We assume that at this point the temperature probe starts registering digitally a temperature change. (3) As soon as the heater bundle activation stops, the temperature of the element drops. (Please see the attached figure of the App. C for predicted thermal response). We assume that the probe temperature levels off since a drop in heater radiation can no longer support temperature increases while conduction distributes the metal heat throughout the pressurizer. (4) One difficulty in determining activation / deactivation is that it takes at least 3.5'F temperature change (dead band) before it will be digitally recorded as a change. Thus in our example below, the temperature could ~ hive continued to rise after 03.21:45 to 145.6* indicating a longer heater activation or it could have dropped to 139*6. We assume that-the heaters were deactivated as soon as'the temperature of the probe levels off. With these assumptions, we perform a sample calculation. It should be noted that for consistency purposes, the heater was considered to have been turned on as soon as a temperature increase is reordered. Similarly, the heater is considered to be turned off as soon as the temperature of the probe levels O

hl-L(b le s s 'o 0 off. To this time, 1.5 minutes were added to account for the initial delay it took for the heater element to reach 1100 F. The heat flow (Btu /h) calculation is based on 1.5 heater banks (57 elements), a bank having 39 elements with each element producing 14KW. Every time a set of three elements was racked out or racked back 3x14KW was subtracted or added to the listed heat flow.

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• o PDS-21036 3 (9 84) o Babcock & WHcox a MCDermott Company Nuclear Power Division ooc i o-Ts r i TEwP C3:13:30 79.73 03:13: 45 79.73 03:14: 00 79.73 03:14: 15 79.73 03:14: 30 79.73 03:14:45 79.73 03:15:00 79.73 03:15:15 79.73 03: 15:30 79.73 03:15: 45 HE*Ti"

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F BWNP 20697 (6-85 l Babcock &Wilcox DOCUMENT

SUMMARY

SHEET a McDermott company 32-Ilfo 7 7 -0D D0cVMENT IDENTIFIER TITLv SMUb PR HEATER RA1)lANT GNER6'l T)ls7RIBUTl0N PREPARED BY: REVIEWED BY: R.9. 8Rou]FJELL R. E. Cl AR K. Nmr nar s GNATUR SIGNATURr 2/![7 Tm r [4 O/ Md. DATEWY/9A TrTLr M6tML NAT8* DATE 3 REF. PAGE(s) REVIE VER DEPEN EN cost CENTER PURPOSE AND

SUMMARY

OF RESULTS: THE PURPOSE OF THIS AN ALySsS IS To F'oRMULATE AMO CALCOLATE TVE RADI ANT GHER&Y DISTRIBUTIDM IN TN 2 l PREGSCRIGGR FROM THE PRE %cRIEEg HerrER BUNDLES FOR rye SM oD PuNr, AbD To LOCATE THE M AMIMUWI (HOT Spar) P0lN'f5 0F THAT DISTRI807/Chl. j ASSUMES RADIATloy 8F ENERSy FROM THE 'Tue cAtcou ATiD^) LATERAL SURPACES 6F THE HEATER $]UNOLE ONLY, NO RADIATIoAl IS A660MGI) PReM THE WEATER ENb5 Ti4E BuMut E IC -TREATED /.f A C'It-I Ar0RicAL HEAT CooRcE, AMD THE PREG 0RitER,2 4 guck geny R16HT ctRcoLAR C YLINDER,. TWO HEATER LENCTRS A650R6eR A ARE USED To AcabodT FDR Po6618LE HEATElz 6xPAMStoNLEW4THWISE, J 'T*VE RESUCTS ARE A TTACHED, THE MAxigA (hot S9015] Occur th THE PuuE OI= THE WEATER BONDLE, IveAR TIAE ENDS OF THE HL 'TG) LEN6TH 6F THE HEATERS, THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT: CODE / VERSION / REV CODE / VERSION / REV mst./9 PAGF OF ~

r POS 21036-3 (9-84) GENERAL CALCULATIONS i sancock a wiscox a McDermott company Il4NW Nuclear Power Division Doc. i.D. PURPoGE OF Analysis l THIS ANALYSIG PRout DGs A MA TN Ef44TICA L. l (40 BEL i~o R C A LCuL ATIU S THE RADIANT NEAT l GLux FRom A HEATER 8vNDLE IMPIN&lAf6 OW l THE 014LLS of A C VL /AIDRJLAl-PRESSURi2GR, l UtE S5 5 L s CEcotJbLY, LT CALCOLATEs THE Posirion of TfiE RELAT WE Nl A%/M A of Tmt fLvx ju eRDER. U SCGL. TO LCCATE HC SPOTS ON THE LUALLS C5 Tl/G E T5E DATA PRotti DED 8y rHIS AUAL Ysit Lotu. 8E UGEb IN AN EN6fN EERINS ANALYCIC TO CALL,ULATE THE A.ESULTlNS TE)VIPERATuk E DISTR 160Tl0N IIV THE thALLS oF TRE VEssg[ DOR,iM6 A Al ~ EUENT IN lu titCH THE H EATEkS LuERE EN ER6 LEE *D Lu dit E NOT Su6MER6ED IN LUKTER, hG50!cPTIONG 0 SED

• THE H EAT 6009CE IS A sin &LE C'tLIMDRIcAt 80NDLE luMICH RADIKiES IlEAT AS A 8t.Ack. %DY S009.cE UIhFcRML];

y i e TiWi PREGOR14ER UESSEL ts A RI64T c.tRcuLAR cyLiAOEQ t IAIRICl4 A%0R85 ALL. ItAPIAiGIN6 RADIATI.oN As A l St,AcK SODY M EAT C/NR,

• TkE HEATER, 80tJDLE GND FAGS b0 M6T RADjATE ENER6X DOE To UNHEAT6D METAL OR INfol.AT/c4 l

AT EITHER. END of TH E QUNDLGjCoMPARGb lu TH s l nacs. 6M w& R. /2 S PREPARED SY DATE

F POS 21036 3 (9-84) GENERAL CALCULATIONS i ancock a wiscox a McDermott Company l 3 2-~I!b W l Nuclear Power Division o o c. i.o. I 1 THE Tutta m erat. o u r it E La,Enta_ saapAces op THE H EATER 6. THE ' RADi ANT ENER6Y DisTRl6tlilcN ON TkE LUALLS AT OR A800E T nc Pi ANE of TDE HEATEk 80rJDLE tG THE NoST trJTEtisE. 6 ELDLv THE HEATEQ @utJblE tuas A IVIA GS 0 F LUATER CU9tcil lC Ar] EWECTidE NEAT EiliK PREJENDU& NON UM For<M HEwh6 of ThE LOLUER U ESCEL VJ Al-LG, T HE GE6mETFlv UsEb IC SHctutJ ttJ FiGur<E L AtJD DomENGlous; USEb ARE GivEtJ ltJ T48iE d, CONSERTs \\/ELy Lotis HEATED t-Ell &TRS WERE USED To E FFGCT MINit4UM 'DIGTAtJCE FROM HEATED suppACE To TRE V E~GGEl tu Au.5, MEucE PRcDxing. IVl44: Mcm iMPiIJ&tN& RADIANT HEAT Fi UK

LOCALLV, 1

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F POS-21036 3 (9 84) GENERAL CALCULATIONS l Babcock & Wilcox 4 MCDermott company l 30 'IIS 7k78- 00 l Nuclear Power Division ooc. i.o. l! I Rgsuurs l THE M A xlh1 UIVI HEAT FLUX OCC*URS ON TllG l PR.ESSURIZER tuAt.L closE To ThE Gr/Os of rNE HEATGR 60n 0 L E. ZT sS VERY CLOSG To TkE PoIN T. lyMERG THE M s MI A40uj DI6TANc6 gETWEEN WALL AND 8vnDt.E Exists. AS SHoWN IN THE SKET&WEC BEMill, THE WALL of.AeouT 6 6S* i=ROWg THE BuMOLE Cl= HEATEM PoR A flW HEneb LEMorn of 40.C# AN0 % 16

• FAR. A HALp HEGGD t EM7H 05 4/,9 ".

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PDS-21036 3 (9-84) saw=_k m ax GENERAL CALCULATIONS Ii o. M -O b 7978 - N Nuclear Power Division o o c. i.o. O Resvers, cowrb \\ l THE W87FwX t3 A600T B,194 x 10 +/m'-S ~ A vERME rk THE 9uMG on THE MEJ7EM FoK A HNF h'GTsa igx 6TH of 40 5, I l pse A auc agrey Lsx67H of: 41 0 ThS AUGRe66 acaesses ro g a x is%1.- s. rue uwen sanue sS Duc To LowCR 300RcE PowGR DENSIT>' oJGR + we'GR-4.Gd&TM. THis CASE Hov60ER,. HAS THE Hi& HEST PGex fl.0X; I.I x 10'+/sn* S. .~ i 8 e 1 E M 8 O m d) o,,2h/f 7 fM LEAL ,,,,1 A by W25 ,,- -,o

V P05 21037 5 f9+ Babcock & Wilcox 1 a ucoermat eemo.ny Nuclear Power Division M-Il4 7W -00 8 I i 1,= I +l = .....j.. g l l l g....-.;. .r. ec i _ __ .,Q~ - .a.. g.7...;_.. - t..- _ .gg / l .i.. Wl = > )& .... l Suom t --6 j. 1 1

i. '

l TOP VIEW.. SIDE VIEW ~ '. n e L_ t+St U d = R-h Q = R -A e [=IR2-p 2 -f p. f$ = H f / ~.Y.. 9, 2. 2 y MEATER ~ ~ ' If Gonous \\ f M-~ __p_gggy e,v \\ + s MDLE ! f' .. --.....-... PESSoc. tug @ t .$ h... = I, p TOP VIEW SIDE view F I G U R E 1. Geom evn ic Cou plGU RATIO N flTLE DOC. NO. 32-Is'M7ff40 PaAtAut6Souafhkin 5RM f.Old & n GNS RED BY D it ltWED Bf Daft PAGE NO.

r POS 21036 3 (9-84) ancock a wucox GENERAL CALCULATIONS li a McDermott Comparty /6 -00 Nuclear Power Division o.c. i.o. TME Dita E M%IDMS USED A&G GlJ EN 6 Es-O ld, The f} LAR6ER \\/ALUE OF H WAG USEb To flT A 6 x 6" klobG' SPACING ON 7kE PhR WA tJ.. DuSuRVATIVEs.Y l AME RAbids OF THE I4GATER 6ualDLE, Q AND /4 GATED WAt-F l-MN67H WELE USED TO INSORE 14IdlMoyl CPA CIN 6 TRoM TRG 9RE$dRl2ER trJALL (DIMENS/0HS C$,6, Or ~E sn Fs&dRE L), T)lMEnSivJ DESCR:Vis og v'ME Base REFEREuce IN FilsURE t USED \\fALul R 92R SHEU. RADIOS 42" 4 1.' 2,6 H yeleur 6s m nEAo 372.# . 9 0.375 2 A wt uEaens O AuseA6e kE4,an 7.33" 9.227d'4x 3 Sonos.E RADIUS 6.I70%n f E EFFEC 7tus HEDED g 4 @.6 ~ 40.17%$u 7 u:MTH OF MDLE 4I @# d n,a,- O anut nom u6 451l',', SoNOLE To W A u. O !4I7 END TO W AU. 06 CStiER'sME E,$ ## l DISTANCE FR0ks RONDLE l. f g s' 8 OtSTAEE Fff.oht 80NDLn Q,ggfp To n>nu. ar s>au.e L in g, ggg E tob SuffoRT TAFoLE 'I. T)IM EH S I DNS USGb IN /MALYSIS kMd b oar, ZNb 7b5 r ,,*i,o ,v ,,,,,...,, (AM f /%A ..,, bA/n .., ~..

r i POS 21036 3 (9-84) sancock a wiscox GENERAL CALCULATIONS ' a McDermott company 8' 3 11 '7 00 Nuclear Power Division o o c. i.o. 3 N THo05 UCED E

• A PORTAULA FoR Tl4E RADIArqT HEAT FLUX AT I

ANY PolhT Ita SPACE LUAG DERtJED FROM l' Tne RADIANT H E47 TRattsFER TEMT O F SiE&EL AtJ D Mou) ELL, R EFERENCE L, i THis FORT 4ULATlord //J(/oLUE5 A i)ouSLE I/47EGRAi OUEtt THE 50RFA< E OF TH E HEATER 30NOLE, TkE FOR!^ULATloN lu AS SPEclpicAU.y APPUGD To TM E GEottl ET RY OF THE HEATER idutJOLE AND PR E%onsteR <>uAus, THE REcouriHG ExpREsstaN

Fog, RADl Arn H EAT -FLU X AMAkYTICALLY R.E DU CED To A

Sit /6E It/TEGRAL Furq crio N. h PROGRAM luAS WRIITEtJ OtJ ~1HE C^uc 765 //d FORT.RAN E lO NIGH INTE4RATEi) THE ~ RADlANT FLU)(, OUER THE OPPER HALF OF TAE PRezoRn2ER UJALLS AtJD Top A800E THE HEATER PLANE TO GET TRE T6TAL. EtJERG)r A8COR8ED 8Y 60RFeE5 TH EQ.E. A lioRMALI2lly FAcioR OF G 5/rhiEGRAL LUAS CALCU LATED i Tid EA=ECT ThIS STE P A360M&S fc R of THE HEATER Peu)ER IS RADIATED l Il4To THE UPPERHALF 0F Tne PREssoqi2ER A60VETHE NEATER PLANE. A 6EcottD PRodrRAld oN THE CDC 75f CALCULATGD TAE RAD /4/47 PLdx distr /8uTion oven.Tns l tvALLS Atau Top <FLAliE OF Tile fREGGURiEEk r QV TkE NoRidALiQlN6 FAC7sR. CALCDLATB A8kg,duiT l tnt 5 FLUX Dl6TRl8tT/tN _15 m FR4cTl0N OF HEATER Pou>sq. PER UMT ARE4 AESoRBED BY TAE SURFACE, But Bl+osau ,,,,2/9/77 Ebd r ud .,, 1A h o 1 b5

m PDS 21036-3 (9-84) GENERAL CALCULATIONS j sancock a wiscox 4 McDerrnott Company I W Nuclear Power Division ooc. i.o. l 8oiil PRDGR4tdG UGED TkE ROMBEM IhT24;gATIN.1 l 0 TECllNIPOE WiTH COMTAE RCIAL 506ROJTINE S FRolti THE TMSL M ATilEM ATICA L Lt 6RAR Y, o rHE INTE6 RATION TEc4M/ %'E WAG C HECK ED Trib EP EN DEtrTLy A tJALYTICALLY AbiD TRE y ORI 6 tN A L. s=LU X \\EXPREGION LU As CALGOLATED USIll & A D006LE IhTE.GRATIcN 20MINE T6 U ERI Fy R.E6uc.76 8Y Tul0 M ETNODS OF r40MERict L ItiT EgRATichl, 8 THE FitML iiEAT FLuy. Ol6TRIBvTl0tv WAS REVIE(UED FOR H oT SPo75, ThWE FooND NEAR TRE EMD oF THE HEATER 6cNOuE WERE RE CALCULATED DIV A tkgE local RE& ion T6 ASTORE TitoRoL6H CDUERA6E OP hot GPOT RE&ieuS. ~ c&E HEAT l~t U X DtSTR18 UTICN LUAS REbot16 UGING A SEccriD LA Ra ER E FFGCi td E HEATER LEN6Tli - l likt 8&a-al ,,,, 2 W n (6 L 2 E. i % L ,,,, hM ') Rl25 L L

C POS 21036 3 (9-841 sabcock a wiscox GENERAL CALCULATIONS ! 3 a McDermott Comparty l W Nuclear Power Division o o c. i.o. I bl5COS51Cl4 OEkTECTtVES ai; ANALYSIS TkG OSTECTlU6S IN THIS TASR ARE : 1. l=0 RuvL. ATE A M A Tile N ATic AL M0 DEL peg j RADIANT HEA T l= LUX IMPthi& LNG ON THE LUAUS op Tile DRESSURIEER U Gss Ef, P R otA T il G PR ESSORI EER H G ATER

5coRcE, 2..

"6 Eu ELOP A un5THoD FalQ CALCULATIN6 Tile flEAT Flur DISTRIBUTION OlV THE INGibE 0F THE PKussuRI2ER Luau s USIAlb THE Nio BEL.iN 1, 'd, CALGOLATE TH E HEtr Ft vX DISTRIBUTIots oAl TR& PR.ESGuRs 2 GR Lu ALLS AND LOCATG THE Hoi SPois oF M Axiuutti IN TEtt git V k, i THE DISTRISUTtoM lutLL. 6G Al0RtAa.12GD To THE Pol 0ER ci= TkG PREWORi4Eg HEATERS Go ThG TOTAL Poulez CALcutA759 gy iNTE64.ATltl6-THE llETI FLUX OuER ALL JNGoDE SUAi= ACES OF THE fR250Ri4ER 16 QNE DAIIT. 1 1 I?sd B P4raad! ,,,, W9/g'1 l !9M L 8Aad H'9/P9 IOl25 a,, a, o. l

) PDS 21036 3 (9-84) GENERAL CALCULATIONS i sancock a wiscox a McDermott company l -i 00 ] Nuclear Power Division o o c. i.o. FORMULATiora oF M ODEL FOR. RADIAr4T HEAT FLUX

t TECTiotJ

'i-3 oe Rer,1 v <<Egmet actaT,cn u E4.T T R AtJ5FER ", bEFItJES T11E '64 Sic LAto FDR RAblATED Eta ER6Y GtcuAri6-2 6GTwEEtJ Two EL Eh1EtiTS O C; EJ R FAG.E A R.EA, EQUATIclJ 'I-3 OG R.EF* L IliDICATES TkE EliERQ ?ER UliIT TtinE LEMiNf c} hg Wiilcd i5 stiClDENT UPCl4 dhz 16 6(UE4 6Y (lj; ci 'p = k (cl Au coss,)(eir.cose.) (t] S* @i 15 Tite Ati6LE 6EibEEta THE Netta Al, To dAg AND ~ 7kE LJ'4E OF E16HT 6ETWEE4 dA AtJD d41. i k iG 7kE At/ft.E B ETWE tt. 7 H E rJORt4 A t-10 5 A-AIJD TliE SA14E L/*E OF El647 8EituEEN ThE TWO AREA ElAMENT5 5 Is -rne dis,AncE 6erweEu TRE Tw AREr EwaEnis K t3 A Futec11cta os=' TEMPERATURE, MATERIAL. PRcPERTIES, Arid A FAcicR OF }ht TO AccoutJT FOR RMIATierJ OF EIJERS Y lNTG OllL >f ONE k Et4t SPflERE FRota TkE l SOcacE, d Au, IIi l g k h\\ \\ Q W y gc.e WQ (, BER MNM o.r. 2hh/7 LM L e6L ..,. u's/n lll%-

POS 21036 3 (9-84) GENERAL CALCULATIONSl se=* a wn=x 4 MCDermott Comparty -If$7 ~Vd Nuclear Power Division o o c. i.o. I KdA lS THE SdDRcE lil7 ENSITY) T//' EMERGY PER 0141T TIklE PER 11EMISPHERE l RAl)i ATEb FRoul dA l i T>PICALLy' k= G (2). l 27 wkERE D* = STEFM-6'otJEtdstaN CotisiANT, A I MATErstAL PROPERTY I T= TEt@ERATURE OF clAs KdA rnss, t2 Tite traENSITY of THE SaoecE Ac GEEIJ g FRDtA ThE A6SOR'6ER. oR GINx, dA2. k dA Co6% is THE ENER6Y PER vizi7 Titt1E AER ONi7 AREA i S* AUlviN6 Ar dA2. FRcM dA s y OR.liEAT FLUW cl A 606fh. 15 TkE EiTECTIVE CRoCC SECTsot/4L ARE4 oF 2 ~8Y inE RADI4TEb EriER6Y Al dA G EEtc z ti ARRIG5 AT dA2.. I (d A Cossi d A CosG i d#iT 4 D s THE ENER4y PER MENcE i i t \\ S1 ) Time ABGM:6Eb BY dAs l l l $t 5 K SIMPLE TEST oF THESE 69t!ATibl+S V0R T U E I PoR90sES oG TUIS ANALYSIS,4 lift 4ISPl/ERE 6F RA CALGULATE How MUcd Erd E R6rY I5 A650R6ED 6y~ f FoK 4 SIMPLE S00RcG ELEMENT dAg * \\ i 4 b_.. 6 KETCH OF Y r d& p HEMISPHERE EMIN$ "p 560Abt d A; 5 x YO eneraneo av oare 8 neviewoo sv oArt P AG E -N O,

9 POS 21036-3 (9-84) GENERAL CALCULATIONS I Babcock & Wilcox a MCDermott Compatty 'D'lld7' b~OO l Nuclear Power Division o o c. i.o. t I t oR UPHERIC4L. CoORDih47c6,,TI(E EL.EtelEAri oF 60RFu.E A E.E4 lS d dz.: (Cd$[(' C,'n H d9).pt^$ % ds N g\\kinWd6 Sk'act ' OT clA {j 4 i l 'J]nEusay 1Tf \\ gl dAl I T 46 E ; 43 = % 3 , d., i O B, = O* e't'e'"" M ssngas i = t^ ^i THEN TRE EriERGY PER:Uti. T Til<lE CAP 70R.ED BY A Ne4 SPMERE CEtiT ER.ED ' OVER T146 Source clAs iG GufEN 6Y ($) l MP fi [E MA,Y o [(dS[fdf8d6 [f E C u25 f .C',) \\ a O

.H Tz E' =

C*T dAs Cos% Gin 9'bWO6 = UTkAt s fi[ o O d' = O*'1' = TOTAL E!4ERGY PER OtisT Tit <tE RADIMED 8Y d As. TilEREFcRE, AtiY HEkIISFhERE CEhTERED CJER THE SOURCE [ VJovi.D CA PickE, A t.L. THE EttER6Y R40/ATED RE64RbLESS OF TM6 R ADIUS, C, TVE Fo RIA0i M 10lJ IS Affko9R14TG FOR 06E H EREId FoR A B A ct< 60DV A660RBING. ALL. RADI ANT HEAT INC i DENT UPotv l'T o. 87 p. e. o e v. o 1, tow E, dM A/P'> /3/25 o... p..,.. ,,,,...o

c POS 21036 3 (9 84) san =ck a wncox GENERAL CALCULATIONS i a McDermott comparty e 39.-Il4W W -00 l Nuclear Power Division noc. i.o. fI} AHb hi) CAN TRE RADIANT HEATuW G su Eu IN 6g WRimgu

u Mogs seEcf pic pogf<j 0$j//g.

j LaoRDIAi4TES i=0RTkE G Eor <lETRY GIV6td Ihl FIGURE 1 i AND SkolutJ h!/ ALYT/C ALL V Ia FI60RE R, 1 1 ok ss r u ti tT UELTck PoitiTir16 FRWu Po:1T Pg ou que s HEAT Sc0Rc5 70 7eiar R nu 145 gjsi.L. lf-fg Alio S = ( ?,-Ts n:,ns ausisisce esor<1 souace yoinT, Ps, To TRE Lu Ad. Polni, Po bc*f io-N AS A M PP.oDJCT. ~T hEtt CDG65= .IPo-Esl HErac.E f4E H EAT 3: w / A T fc8hT k Den TO 4 S0NE Et.htMrsT AT 908teT 'Pg is c) F. KCoS9s d As k J As II:;-Q-Ps) _, ( ' 'SS g _ Q I f' - E l*; o KVisdfo-Pd clAs b OR cl F = 3 > Co-Cs THE C00RDt!JATEG USED AR6 C Yt I!JbRICAL AS SkoWN in i=I 6 0 R E 9, ! Xs = fcosG 4: Rcosgr og= csin e o=o o Ys = to No sing e clAs= t'd907s kM N

o.. I9/O es-r t. eAL o.,, iM9 I4-kT

,,,,,,,o,

. ~. .._.e. y POS 21037 9 (9-b Babcock & Wilcox 4 McDermott Cornpany i 3 9 - l l s W M _.0 0... -. Nuclear Power Division ... ~... i 6 i l.* t )..... ....i .I. .._.~~ j Poivt 09 t. .j_. ; .. WALL 3 I. .;.Pg.g.g ....p i. i ........j. g. j.... ;_.. 7 j ggRWLAL'.' J. (, '~ ~ 4g ... }. ~ A LL" _. ~

• ~ ~ ' " ' ' ~

w .5... f... g. .. l. L~ ]~' PolRT.odc0RcE._ ~ .((y'.. p l. P(x3 1 ~ 3 a j l Us ..t- ~ -l; ~~T.. . NEATER - ~ .J soum.e p 1 u#*

• r

.N N g g \\ D. k .,4 \\ s i N 9 N / . bo* EObN. f3bN 0s :coS01. + sine j EADIU$ OF LUAL(,. f I RADIUS OF NEATEit ' EONDLE ~ ~ ~ ~ p. [ 5 5 5U h O k.VEcToft-ro.Pos9T.oy.fodecE. b 5 s --' " PRE 550RilER WALL "- -- 9 4 4 2 k VEdeR 70 Polui 04 WALT 0 o - " - ' ~ ~ - R OM Polk Y o $ 0 t' 55 g* 5 s ~ 04 644:( 79 fotNrod WALL GEOMETRY. AND CooR0 #nES FOR H EAT Foox Dl5TR16ttr 04 OAl Wdll-5 D OC. NO. TITLt 9.-ll(797F-00 PatPAttD SY Daft AtYl WE0 SY OATE PAGE NO.

'D5-21037 5 (St. Babcock & Wilcox a McDermott compary Nuclear Power Division 3 9. lff l'J([7 F 0 0 -=. l i i l -l Qi

1. .M!I -.- N I..

O N '- i. I .Y ) j j-.. .i =35 I. = N__.4.. ~ s. [._... j 14 g,2. .t fE.. t...._. i ..[( gfALL_ _ l i L.. L g i._. -! - 3 ._3 g @.._.. ; -~ . X-F---! goe y;

-.x. I

_ /_. 4 .~. ,.g ..g y,s Y' v. __...... -s g

y

/ e4 +. (b / ---M V ..y y... A -U \\ GI 1 b s 4b s Hou.ViSt = . fcgitert o -r '._fodRG FRcM . POIMT 8 i END VIEW OF go,ggg g FIGURE 3 LIMITS oF INTEGRAL. 09 Source HEATER BONDL.E TIT L E DOC. NO. g1-1(d7978-00 PetPAie%Ft6 L ehhh wrs. eLDMi id?S Daft RtVitWED BY Daft PAGE NO.

e POS 21036 3 (9 84) sancock a wiscox GENERAL CALCULATIONS a McDermott company ~IIS W'OO Nuclear Power Division o o c. i.o. THE H EAT flu % t /Jc ! D E/JT AT Poin7 Po 16 6IVEM 6Y (6), id OLTI PLY l MG T415 BY T4E C66/#6 oF f gb Thy T4E AN6LE f3 ETtuEEM T4E NORM AL ho(lo LINE OF S/6H7 6ETwEEN 9 AND UESTNE 5 iNCI DENT RADIANT ENER&V A660R6ED PER UNIT ARE4 cl F. J F,.= Kiis. (F,-h'l J43 iio, (F,-7,) TCo-?sl3 lPo-?s[ THERE roRE JF= K ( iis,(r,-r))[iio-(f-hj Jk ['7] i s o o Fs* UTE6RAllN 4 Ali Cot 4TRI60Tl0Rf PROM THE HEETER. 60HDLE TH E TOTAL HE4T Flux. A66dR8EV 6Y T4E W AlL 'PER Ull:7 AREA IM UN ITS OF Enik%Y/Ulsii TIME /0Mir AREA i5 { klhsdtdsL{IIo.(FJ&clAs 7" = Iio'Esf J 61nt 01= 60646 Vl61SLE Fem F, 205T H0M To DE6CRI6E TkB Sc0RGE IR O M T li E. \\llEUlfbluT OF THE POINT ON THE WAU I3 SybWH ly FIGURE 3, 6, 'AND G1 ARE TkE M6t.E5 6ETl0EEM LvHICH Q MOST (fARY Tik 2 CooRb/N4TE ON THE SodRCE M !! 7 r., PAR,,,Y

DAT, MLat & e1A

,,,, zA/n I7/9S

~ Po$ 21036 3 (9 84) ~ s.acock a wucox GENERAL CALCULATIONS a McDermott Company ~bW ~ Nuclear Power Division o o c. i.o. VARIES FROM --), ro ft, w THis AdaySis '- k i Q= TAM ~ D6 ?l-I (FI6,h (f %= m-'(pho) + cos-'(r/Ex;g (esss) m = ncoss, n = cas Cms.c (q \\ E, c Rcmg 7 gs = ca.9 ( Fl6,2.) J h G2. \\ -(lcose(xh)+sune(gst Cosf6(xhl4su)M(1,-$,dAi [(NMJg=Us [)o- + b o-4 (?o-2(( -l G, baunouvin& To Su6sTIME PsR Ys, }fsy AuD, MD, GINid ; 1(01 Fg o ) K..M6 [ ^4 -rese) + M9(b-C 'ded, * '" _j, g,. - Q ( x, - rme) + t c e. - M2 raen, o EC % -rcosef+(g-Psinef+l 2,-Es@ h 01 , Fa = K [%Cose +Sseue-rDA-rcose)--h[Es4 ~f,

wcuseuys,,e+ a,-w y

-se n a m eaavaa -,ava,n w arv.,~r u.,g.s.) OW 'fk E WALL =. pa,PAtt0 SY O AT, LLuf f Abd- .,, 2Ah 9 M/25

r~- o. PDS 21036 3 (9 84) s.acock a wiscox GENERAL CALCULATIONS i a McDermott company i -l W -00 Nuclear Power Division o o c. i.o. 7015 IG RiEh0C Eh To r{iE FORM i t 2. F:E.C A + 3(F,;. 2o) c G c4 [li) l a (a:1.u.s) R p ,+ (%s'Q. fc C '), G, t A= %c(%- Ccos G)(% Gase + Lo s/u 9 -() c 3= -Z (Xo cose + Uo sine-r) o c d= l (x -rcose[NO -r slN B[ o o c AND A SU66TITUTierJ 'Zg-%o =fA N h REDUCES ti FUR.T H ER To ', Ed 2., Fa. = Vf' - ()t, 4(-],j c e ;gsneo (I2) (wm] R par now 9 P.(ng,p) on rue tuu.L - -\\(s!= A rsu~YQ f)o +1fE~N (nkece s ac <c w,u c q c w. Q, c4-$ j (c c4-t '3 L _g k: TAN Xo o n ,, p a d 8 L a d .,,1 Min ,,.Lwq. t%L ,,,, rNn M/W

W:. -[ *. N PDS 21036-3 (9 84) s ec==a m cox GENERAL CALCULATIONS i a MCOttm0*t compepy FA-I 6 ??W -00 g s tvuclear Power Divi [sion ooc. i.o. s, ~ DEUELDPmENT FRom Ey'X!ATI011 [7) SimIL4R 7O = (il) h^iD {l*L) (U AG 1)0tlE FoR THE TOP PUNg }l AT THE Top o f rye PR.sssuRIQ.Gg LAJ ALLC, l TkE SECM GTRY USED 15 Shou)H IN FI6URE 4, ll .I ine Resuccons eper tous n.g } h% ...i K _cose(N-x Jmugdg4qs)rdecig 65 ^ Fa. = s Wh \\&4 Qiks?Al -Q)f g ,, (;g t A60 CREED E14EE6Y PER 0t n T:t4E P E R u ts ii t.REl. ~ kt(- ~ ^ ' r K ~ ncsss u sita-d(qc-rsind dsJy Fa = N [(x ecosey.. '6gersmef4 (3eg (;cpput.s) -z 1 Jf r + -1, % i f Oz . Fa. .= (K D ded2, {j4 l (TOP rat 4E) 'T i t s C +(Era m -k G, WRER.E D:[XcGo60 + l o 6/h6-I o-I'6(IM) @ = &c-rcosf+ (c csins[ ) c t Q = F{ s c.ot*STANT I 43,,g Ac uerit<co //e[/2j-s rat 6 %nnaN ..,, 2N/19 EJxs. p InL ,,,, LNe p 20/25

~ ~.... PDS.210374 G-6.'- Babcock & WHcox 0 a McDermott company 3;)-ll['M N QQ _...._. Nuclear Power Division .3 l-e 5 I .g )i g j.... > h ' t ~~ .'. ror PW _ ' ~ ~.~ ~ ~ ~ ~ ' '. 1 t Q .t-l ... - - g .j j. p.g.gp7 _...,_...__j r-g r .l .-....7 C i

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f..

gf ./ Q~ t I.,._. ;.. / q_ l l ,i_..

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s. - ~ ? l y AGUJUffilff ~ g IVM.s. s .. i l / / I / ~ l ~ ' ~~ s w / ~ ~ Is ' N' c .l. e .p /c y l ... _.. 0

• CA6 0 En 4 SIN %j 5

j Mo // TOF Fs, Ara! r .t 3sk "M9 i4 MI6 f 4 2 ~ ~ ~ ~ '-~~~~ '-~% =~%3i+ Us _. ?g bl 4hg 4M = cosN + Uo7 + ("Il ....._..__._( ( U = h, ou W PLME (o 1:l G U R E /r-Top PLAN E GEo M ETRY AND CodR,bl A1 ATIES i DOC. NO. Wl978-00 TITLg WI Daft A WED BY Daft PAGE NO. PARPAbO BY. stb %dhMn flvo u -1.c M M b Ll45 .-,n a ,-. - -. ~ .n. .---e -..,.,---..n, ---...,..~,_w,.

POS 21036 3 (9 84) Babcock & WHcox GENERAL CALCULATIONS i a uco.rmaicomo.ny Nuclear Power Division ooc. i.o. .I DTEGRATIN6 Ot' 'ls Ih ll*] Gz l r K }FlT(L., - bit (-), je (i5) Fa

== (. top Mis) J l Luiine HT(q I = D___ i utI(E-4)/' + (E-2J 7 2CI _C i -c J~E-Zy'd]J T)= (wcose + v r,r e-r)Cu -rser.e) o c c t C "= (w-rcose)1 + (g-rsinej s u

z. o=

H, ^X n =: Q CDGF, %= 0 SitiV 05% SClo* j; - Qt = k = H ExieR. hat.F LettGin c<= TAti'(Lijyo) = GoG k f/&+ gh ~ j 0 = c< - 3 91= c<+is I (> ( l EQUAT1005 FOR Q A666R8Eb ENERfy PER ouiT TttsE PER UNIT ARh4 ON top PLANE. o f?bd 8 La0 ., 2M39 ,,,,,,,,.,,, (Ab<ts eb& A/t9 22 M- .a.,

O PDS-21036 3 (9 84) secock a wiscox GENERAL CALCULATIONS a McDermott company 3 --ll6 D0 Nuclear Power Division o o c. i.o. IQET HDD F0R CALC 0VATlhi6-l-iEAT t= LUX DISTRI8 UTIelj " oRIA SuourM IN THE ATTACHEb FICHE PROGRAIA M CALcui-AT EG THE INTESR4L 0F THE A 6CoRBE D ENGR.6y PER. Utt IT Tit <t E ovGR THE uPPGR. SUR. FACES OF THE PRE SsuRI2ER A6cvE OR AT THE PLA/JE OF THE HGATGQ %'M bL E, T]iif ItiTES RAL SH00Lb 8E }&, OF ThE HEATER POUJEL 4. pro 6EAM ort [ CAccuLATes " FACTOR tuSERE 'TRAT 15 N j /d FAcToe. = j RdgfA-t p K PER W V9PER PER WA u-.5 TO P Pijng No Rln TliGIJ cat.cuLATES A^tD PRllJT5 0i5/FAciok As ' A 8 r40RIA ALI-2/IJ6 FAcTop H siivce(k}Acrsrl'= (0dfHaise Pea >sR) Pnistcau.i

c,gij o5 V

= uoatsn.!2pv6- = 1 F4 DOR W57ER i>cu>ER FACTOR 'i Now GoT9 tate 6R4's Fau 4MD $.mg DEPEND i O M. THE uM kuousu Pact o R, OF k EpuArtctuS (l2.) Al4 b (g {}, 4tJD y ts Noisi heiggysuGD 8Y l 69): I Il l1syce pro 6R.AM l' EM UD C4LCOLATE5 TH E PR,o DUCT OG THG ll 140RM ALI-2/i46 FACTOR ti AND .Va T0 PRDDUCE TH'E N0RA's)ALI2E[] l ,, PM R[d%d .,,2NM ,,....,, 6PML eM ..,, ann ..... 13/25

. ~. P05 21036 3 (9-84) Babcock & WHcox GENERAL CALCULATIONS i . uco.nnai como.n, 1 I W ~b Nuclear Power Division ooc. i.o. ' H EAT FLUX 'disTRi8uTioN ' i k k= 6_ ii E G E R P W d R HEt.TER Poipt:R, PRd6RArn SMUD" PR.QDOC66 "ThE EllGRD' U PER vria Tir<ig PER tu ot: Supw.E AREh PER viitT HEATEQ 90LMR A%DR8ED 6V TkE T.lRERJ4AL VESSEL. 0 R.FAGE6 i a 0 THE ourpvi 0F 5tdOD 15 GIJEtt AS A FUNCitohi OF J2f FRot4 irl6dRg R Foa Tils tv ALLS J J AH 0, O G Atai) [ FRoul FISOR.E A-FoR. TRE To9 91 ANE, REGO ~iG LUiER.E REFIIJED 6V RetittiIM 5t< IUD Old A Fili &R GR D 14 E4k 7/]E l'vlA%/MUNI 10114T5, 3 Ficd6 ARE rrradED FO R.

• cal.CULAT IN6 THE bi6RJ4ALI2lW6 FACTOR

' IORM# 1)iSTRl80 Tion ott THE (Al Aus Fsg HEs7ED 4 +0f, Aljd 6N TOP PLAME, HALF LEM&Ty 8 FINE MESH Dl57Rf 8 OTION NEAR hot SPo7s iroR 4-l,6# liALF l ENGTH, VINE MESH DIGTRIBUTl0N AIEAR hot GPors o Pog 40,$" H Aw t-EuG7H. Raa eA1 z/9/rp ,,,,. 1+bS ,,,,,,,o o,,

l O PDS-21036 3 (9-84) s.scock a wiscox GENERAL CALCULATIONS i a McDennott company Nuclear Power Division ooc. i.o. 70 -//47 7 -00 l i I ReeeRences: l

d.. TH ERM AL R40l ATion HEAT TRAMSFER hERT $sE4EL AND ToMu Rn Howsu,

McGR4w Hil L,59316 6 19 81 l secoaD EO rrsou y 1sgst o-09-o 2,8LwDei.wsu& 4154 71 E,Rv7,a/g2l'71, G PRessanneeR GENERAt-A RRAM6EM ENT

3. (JLu> 3R4wsuG # I(4-744 E, Rev. 2, s////7f, kEATee Evuous Aste98Lv AND DETAH $

4. 6 L.W Dewous

• I9120SE, I/25/7'2.

I PREGGOR1-2ER At 80113 DRAW 1HS

5. 6L (U ~DRAWIN& # I35490 6, REV.7, bllfD, NEATGR SOMDLE ASGGM8kY /INO DETAILS G. If L.w DRAwsu& # I354156 Rev 2, 9lll70, SHGLL. ASGGM 6t.Y ANO D GYAILS rl, 6Ltu %winH 8735l A envo, 2-l95/72-IMMERsI0At H E4TER d

P ARPAR,o SY .AT. 44tc /42 - .... @@/P'9 M/25' ...~o. ,,,,...8,

r s BwNP 20597 (6-85) hh& Max DOCUMENT

SUMMARY

SHEET o 4 MCoermott Company 32-1167603 00 DOCUMENT IDErmRER PRESSURIZER SHELL TEMPERATURE DUE TO RADIANT HEAT Tip r PREPARED BY: REVIEWED BY: DARRELL E. COSTA NAMr JOHN F. SHEPARD NAMr SIGNATURF SIGNATURF I !8b E!4!8D Tm r ENGR III nATE-Tm6UPERVI ORY ENGR nATF TM STATEMENT: COST CENTER 308 REF. PAGE(S) 7 REVIEWER INDEPENDENCE PURPOSE AND

SUMMARY

OF RESULTS: Purnose: On November 21, 1986 while heating up the pressurizer at Rancho Seco Nuclear Station, the water level in the pressurizer dropped below the level of the upper heater bundle. Additionally, it was conservatively assumed that up to 50 percent of the heater elements in the middle bundle may also have been egosed to an air env i runment. The purpose of this document is to determine shell temperatures near the outboard region of the heater bundle. Temperatures near the heater bundle closure opening are determined in Ref. [1]. The localized shell temperatures due to the possible contact of heater element end and shell are calculated in Ref. [2]. Summa rv of Results: The maximum shell temperatures and temperatures in the region of the RDT probe are tabulated in Table 1 and sunmarized in Figure 1. The maximum shell temperature is 948. It is noted that this value is very conservative, see Section 10. l l THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT: CODE / VERSION / REV CODE / VERSION / REV ANSYS/4.0/e PAGF 1 0F 77 m

1 POS 21036 3 (9 84) s*=* a wu== GENERAL CALC LATIONS 32 1167603 0> Nuclear Power Division ooc. i.o. Record of Revisions EfDf. Descrintion h 0 Original Release 2/9/87 e 6 l l I l !f,! C PHPAHD H oAM E "^"

I POS-21036 3 (9-84) GENERAL.Q6_LQJLATIONS se.cn a mm== a McDermott company 3 2'- 1 1~ 6 7-6 0 3 - 0 0'- Nuclear Power Division o o c. i.o. TABLE OF CONTENTS DESCRIPTIOff M Calculation Data / Transmittal Sheet 1 Record of Revisions 2 Table of Contents 3 1.0 Introduction 4 2.0 Summary of Results 4 3.0 Assumptions 6 4.0 References 7 5.0 Discussion of Analysis 8 6.0 Geometry 8 7.0 Description of Finite Element Model 8 8.0 Thermal Transtent 12 9.0 Thermal Boundary Conditions 15 10.0 Results 17 11.0 Microfiche 26 Appendix A 27 Otc

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POS-21036-3 (9-84) secoca a wue.= GENERAL CALCULATlONS a McDermott company 3 -1147603-00 Nuclear Power Division ooc. i.o. 1.0

Introduction:

On November 21, 1986. while heating up the pressurizer at Rancho Seco Nuclear Station, the water level in the pressurizer dropped below the level of the upper heater bundle. Additionally, it was conservatively assumed that up to 50 percent of the heater elements in the middle bundle may also have been exposed to an air env i ronment. The purpose of this document is to determine shell temperatures near the outboard region of the heater bundle. Temperatures near the heater bundle closure opening are aetermined in Ref. [1]. The localized shell temperatures due to the possible contact of heater element end and shell are calculated in Ref. [2]. 2.0 Summa rv of Results: The maximum shell temperatures and tanperatures in the region of the RDT probe are tabulated in Table 1 and summarized in Figure 1. 0 The maximum shell temperature is 948. l l l l l lK sk,k7 PREPAAED SY DATE f AEVIEWED BY DATE PAot NO. 6

l t ~ FIGURE 1 PRESSU R ZER SF EL__ TEN PERATURE (BASED ON 1.5 EXPOSED BUNDLES) 1 / 1 1 e O.9 i r r J f \\ k / o.8 / j h.( (r\\ g 3 3 -e 0.7 r r 3 si ^ I, l \\ I F" / \\ M/"_ _ _ _ _ i b O.4 i rnvas:. i r_ur yw r w W y^ 4 ,Av .g }ENi+$k 1 01 ~ m d O i i i T i l 0 1 2 3 4 5 0 i BME (HRS) m 0 9 - - - -. ~

e-POS 21036 3 (9-84) = ~ a wncon GENERAL CALCULATIONS 52-1167603-00 Nuclear Power Division o o c. i.o.

3.0 Assumntions

1. The heat flux distribution is symmetrical about the axis of the heater bundle. 2. The bulk fluid temperature in the bottom of the pressurizer is assumed to ramp from 800 0 to 220 over 1 HR of heater on time. It is assumed that the lower bundle on times corresponds to the on times of the middle and upper bundle. 3. This model does not include the 3/16" cladding material. Refs. [1] and [2] show that it is conservative to leave the cladding out. 4. This evaluation assumed that 1.5 heater bundles where exposed to the air envirunment. Appendix A of this document shows that this is a conservative assumption. I f l i hl &l1fd7 PREPAAfD BY Daft , j afvitWED BY Daft P A o't N O. y t

r POS 21036 3 (9-84) - a wucon GENERAL CALCULATIONS 32-1167603-00 Nuclear Power Division ooc. : o. l.0

References:

L. B&W Document No. 32-1167974-00 " Local Heating of PZR Shell Inside Corner," NSS-11. 2. B&W Document No. 32-1167984-00, " Pressurizer Contact Temperature with Heater Element," NSS-ll. 1. 'ANSYS' Computer Code, Engineering Analysis Systems, User's Manual (Rev 4) Volumes I and II, Swanson Analysis Systems, Inc. B&W Document No. NPGD-TM-5% Dated March 1982 (R4ANSYS Rev. E). L. B&W Document No. 51-1167607-00, " Heater Element Activation Time Intervals," NSS-ll. i. B&W Document No. 51-1155656-00, " Standard Correlations for Natural Convection." 5. B&W Document No. 32-1167978-00, "Smud Pressurizer Heater Radiant Energy Distribution," NSS-11 7. B&W Drawing No. 02-135489-E4 " Heater, Balt Details", NSS-ll 3. B&W Drawing No. 02-135484-E10 " Vessel Sub-Ass'y", NSS-ll 3. B&W Drawing No. 02-135483-E7 " Pressurizer List Of Materials", NSS-ll LO. ASME Boiler & Pressurizer Vessel Code,1980 Edition L1. B&W Document # NPGD-TM-500, Dated 2/1981, "NPGMAT", NPGD Material Properties Program Users Manual. Rev 1.0A 1 l l l l PtePAReo of DAfe /!NO Pace' NO. nevieweo av DAre

P05 21036-3 (9 84) Babcock & WHcox GENERAL CALCULATIONS . uco.,,= c-32-1167603-00 Nuclear Power Division C ' "- 5.0 Discussion of Analysis: A three-dimensional thermal analysis is performed using the finite element method as implemented by the "ANSYS" computer code of Ref. [33. The results of the analysis will be in the form of nodal tempe ratu res. These nodal temperatures represent the pressurizer shell temperatures for the given thermal bounda ry conditions. 5.0 Geomtry. The geometry information for the pressurizer shell is taken from references [7] to [93. The information required for this analysis is summarized below. - Shell ID = 84 inches to base metal - Shell thickness = 6.187S inches minimum - The axes of the heater bundles are 21 inches apart vertically and are rotated 40 degrees with respect to each other. - The RlD probe is located 24 inches above the axis of the upper heater bundle and 44 degrees circumf'srentially around the shell. - Shell material is SA 516 Gd 70 The material properties used in this analysis are taken from references [10] and C113. 7.0 Descriotion of Finite Element Model: The finite element model of the pressurizer shell is shown in Figures 2 to 4. l Due to symmetry only a 90 segment of shell was modeled. The modeled height of 0 the pressurizer is 102". This is tall enough to include 15" of water level, the upper and middle bundle elevations, the RDT probe elevation, and an additional 42" to provide a place for the heat to dissipate during the times when the heaters are off. The shell is represented by Isoparametric Thermal Solid Elements (STIF 70). Detailed descriptions of this element may be obtained from Ref. [3] (ANSYS). PREPAttD BY Daft Alvlewt0 SY O ATE Pact NO. U L

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1. - N0DE NUMBERS

@- ELEMENT NUMBERS FIGURE 2 FINITE ELEMENT MODEL GE0 METRY E 7 re.passo e, car. 2h/rw 9 P ,,,,...o

aos a c r s >,a nhk & WIlcox 4 MCDermott comoany 32-1167603-00 Nuclear Power Division 115 113 111 ] 109 107 23 2 FIRST 19 105 17 N0DE AT ELEVATION H heater 15 6801 bundle end 103 13 6401 (node 2423) ' 11 6001 RDT probe / 101 (node 4011) 99 5201 7 ~ A801 97 4401 4001 - RDT probe THETA G 3 95 3601 RADIU[ 3201 24 2801 FE H0 DEL TOP VIEW 2401 - upper bundle N0DE NUMBERS ARE FOR ELEVATION 2001 0.0, NUMBERS INCREASE BY 400 AS ELEVATION INCREASES 1201

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POS 21036-3 (9-84) a== =ck a wn = = GENERAL CALCULATIONS a McDermott company 32-1167603-00 Nuclear Power Division occ. i.o. 3.0 Thermal Transient: The thermal conditions during the Rancho Seco transient are taken from Ref. [4]. A time history of the transient is sisnmarized in Figure 5. The transient used in this analysis is a conservative modified version of that shown in Figure 5. The analyzed transient combines some of the " heater on timss" while eliminating the "of f time" that separated them. The evaluated time history (along with analysis results) is contained in Table 1. A summary of the analyzed transient is given in Figure 6. -s Dsc ihh y> 2mn- ....... / t ,,m.....

- - - - - - - - - - - - - - - - ~ - - - - FIGURE 5 TRANSIENT HEAT FLOW vs. TIME (BASED ON ACTUAL TRANSIENT DATA) 2.8 2.6 2.4 1 2.2 2 I 2 i \\g 1.8 t m !%g 16 O 1.4 N o . w 1.2 -g 1 h 0.8 I) I W O.6 7

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l i. t FIGURE 6 HEAT FLUX (Q) vs TIME (HEAT FOR 1.5 BUNDLES) 1.8 2.6 - 2.4 - 4 2.2 - 2- ~ ~ ~ ~' 1.8 - l aa: INg 1.6 - 2C lii:E 1.4 - m g3 1.2 - I 1_ O.8 - m ~ 0.6 - l ti e O.4 - ~* l -4 ' i O.2 - 8 4 3 3 I I I I I I 0 1 2 3 4 5 -+ TIME (HRS)

POS 21036-3 (9 84) - a wne= GENERAL CALCULATIONS a McDermntt company 32-1167603-00 Nuclear Power DMsion ooc. i.o. 9.0 Thermal anunda rv conditions: The thennal boundary conditions used in this analysis concist of convective heat transfer in the water filled region of the shell and a heat flux (Q) on the remainder of the shell inside diameter. The shell 00, top of model, and bottom of rodel are assumed to be insulated. In addition, for times when the heaters are off the shell ID above the water level is also assumed to be insulatod. The convective heat transfer for the water region is assumed constant at its previcus value. The convective heat transfer coefficients are based on the equations of Ref. [53, Page 5. For Laminar region on a vertical flat plate the film coefficient is: 2 T = ( A.T/L).25 K K2 = BTU /HR-Ft.op t Where: AT = Temperature Dif ference bel; ween shell and fluid L = Plate height, 2 ft. assumed Kt =.55 K2 = From Ref [5] Fig. NC1 0 0 The bulk fluid temperature is assumed to ramp from 80 F to 220 F over 1 HR of 0 0 heater on time. The assumed 6.T's at these temperatures are 1 F and 30 F respectively. The film coefficients are: 2 = (1/2 FT).25 (.55)(46') = 21.3 BTU /HR-Ft.oF 0 0 2 =.1477 BTU /HR-IN OF 2 k20 (30/2).25(.55)(86*) = 93 BTU /HR-Ft 0{ O 0= =.6464 BTU /HR-IN F

• K from Ref. [5] Figure NCl 2

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P05 21036-3 (9-84) s.a <= a wucox GENERAL CALCULATIONS 37-1167603-00 Nuclear Power Division ooc. i.o. The heat flux values used in this analysis are discussed below. The total heat output of the exposed heaters during the abnormal transient is discussed in Section 7.0 and summarized in Table 1 and Figure 6. The pressurizer heater radiant energy distribution for the shell and upper head was determined in Rof. [63. From Ref. [6] the percontage of total heat distributed at any point on the shell is given. The percentages of heat flux on the nodes of the finito element are given in Ref. [6] and in microfiche run haXH. The actual heat fluxos input to the finito element model are determined by 2 multiplying the % Flux /Nodo (1/IN ) from Ref. [63, the total heat flux (BTU /HR) 2 from Table 1, and the projected surface area (IN ) of the nodo. The projected area of internal nodos is (6" X 5.998'") = 35.988 IN. (NOTE: 6" is hoight, 2 5.998" is width along insido circisnferenco.) The projected area for the nodos along the edge of the model is.5 (35.988) = 2 17.994 1N. For listings of actual input values refer to microfiche runs. DK D Af t - z,h 7 A PREPAtto Of AlvitW80 SV OAft PAot NO.

POS-21036 3 (9 to) m a me = GENERAL CALCULATIONS 3 2-1167 6~Q3 - 0 0 Nuclear Power Division Occ. ' o-10.0Baanikat The,,results of,this evaluation are in the form of nodal temperatures. The maximum, nodal te,mperature and nodal temperature representing the RDT probe are tabulated _in, Table 1 (along with total heat flux input). A stamary of the maximum temperatures and probe area temperatures are given in Figure 1. 0 The maximum shell temperature is 948 F and occurs at node 2419 at time 3.7326 h oun.,_,_,,,.. It should he_noted_that.this value is very conservative.,_The.conservatisms used 1n._thit. anal 1sjs,..are gLven below. 1....The heat flux values used are vary conservative. Append,tx A shows that the .resul. ting temperatures from more realistic heat flux, values could reduce 0 this..maximutt.tamperature by more than 200 F. Tha_tcanstant_ times.used in this an'alysts were a conservative representation t .. af._tha_ actual abnormal event.. Heater on times were. combined and the of f . times. between_thatL.were. eliRinkted. A tQt&Lof 29 75_ minutes.of. of.f time . L". soak tima"). was removed-.. 3. The F. E. modal. boundariesm wera assumed to be totally insulated. (i.e., no heat loss. from. metal. to outside envi ronment or back into the. gaseous. medium of the-pressue.tzer).- IrL addition the heat was confined to the material of 102 inch high,. & inch. thick cylinder with only 12 inches of water level. The_ heat-. removing _ capacity.of. the actual. pressurtzer is much greater than this. 4. Ove-to-the-modeb. element. sizes it was. necessary to leave the cladding out of the analysts. Ref.[1] which contains the cladding shows that the -temperature-drop from-the. cladding ID to the base metal ID. is approximately 0 - 50 for-boundarr conditions similar to those used in this. analysis. O'C n/r/tr i PetPAtt0 SV - OAft StVitwt0 ef OAff Pact NO.

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OELTA MAI PRCBE HEAT FLUID MICR0 LOAD f!ME TIME T!ME TEMP TEMP G TEMP FICHE STEP (HRS) (MIN) (MINI (F) tF) (BTU /FR) (F) 4 7 1.675 100.5 1.65 719 362 2150000 166 MDLT 8 1.6835 101.01 0.51 683 350 0 166 MDLT 8 1.6919 101.514 0.504 651 340 0 166 MDLT 8 1.7004 102.024 0.51 627 333 0 166 MDLT 8 1.7089 102.534 0.51 609 328 0 166 MDLT 8 1.7173 103.038 0.504 595 325 0 166 MDLT 8 1.7269 103.614 0.576 582 322 0 166 MDLT 8 1.7397 104.382 0.768 $67 319 0 166 MDLT 8 1.7545 105.27 0.888 554 316 0 166 MDLT 8 1.7736 106.416 1.146 540 313 0 166 MDLT 8 t.7951 107.706 1.29 528 310 0 166 MDLT 8 1.8203 109.218 1.512 517 309 0 166 MDLT 8 1.8517 111.102 1.384 505 307 0 166 MDLT 8 t.8831 112.996 1.884 496 306 0 166 MDLT 8 1.9145 !!4.81 1.884 489 305 0 166 MDLT 8 1.9459 116.754 1.884 484 305 0 166 MDLT 9 1.9542 117.252 0.498 531 322 2436000 182 MBHE 9 1.9626 !!7.756 0.504 572 335 2436000 182 MlHE 9 1.9709 !!8.254 0.498 601 345 2436000 182 MBHE 9 1.9792 118.752 0.498 628 353 2436000 182 M9HE 9 1.9876 119.256 0.504 648 360 2436000 182 M6HE 9 1.9959 119.754 0.498 665 365 2436000 182 M8HE 9 2.007 120.42 0.666 685 372 2436000 182 MBHE 9 2.0209 121.254 0.834 707 379 2436000 182 M3HE 9 2.0348 122.038 0.834 727 386 2436000 182 MBHi 9 2.0487 122.922 0.834 745 392 2436000 182 MSHE 9 2.0626 123.756 0.834 761 398 2436000 182 MBHE 10 2.0684 124.104 0.348 761 398 2006000 190 MBHE 10 2.0741 124.446 0.342 762 399 2006000 190 MBHE 10 2.0971 125.826 1.38 769 402 2006000 190 M8HE 10 2.1201 127.206 1.38 781 408 2006000 190 M9HE 11 2.1287 127.722 0.516 748 397 0 190 MBHE 2.1372 128.232 0.51 718 388 0 190 MBHE 2.1464 128.784 0.552 693 381 0 190 MSHE 11 2.1555 129.33 0.546 675 377 0 190 M9HE 11 2.1646 129.876 0.546 661 373 0 190 MBHE PREPARED 8v OATE

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BWNP-20667 (6 44) TAILE 1 PRESSUR!!ERTRANSIENTDATA (8ASED ON 1.5 EIPOSED 8tNDLE5) DATA MAI PROBE HEAT FLU!D MICR0 LOAD TIME f!ME ilME TEMP TEMP G TEMP FICHE STEP (HR$) IMIN) (MIN) (Fl (F) (liU/HR) (F) 4 11 2.1746 130.476 0.6 648 371 0 190 M8HE 11 2.1889 131.339 0.858 634 367 0 190 M6HE 11 2.2031 132.!!6 0.852 622 365 0 190 MNE 11 2.2209 n3.254 1.068 610 362 0 190 M8HE 11 2.2476 134.956 1.602 595 359 0 190 M8HE 11 2.2743 136.458 1.602 584 358 0 19.' R4HE 12 2 2831 136.986 0.528 618 370 1862300 202 MAKO 12 2.2918 137.509 0.522 648 380 1862300 202 MAKO 12 2.3(06 138.036 0.528 671 388 1862300 202 MAKO 12 2.3M3 138.558 0.522 688 394 1862300 202 MAKD 12 2.3181 139.006 0.528 703 398 1862300 202 MAKO 12 2.329 139.7% 0.654 718 403 1L2300 202 MAK0 12 2.3399 1(0.314 0.654 730 40f 1862300 202 MAKO 12 2.3618 141.7M l.314 753 416 1862300 202 MAKO 13 2.3703 142.218 0.51 726 4C' 0 202 MAKO 13 2.3789 142.734 0.516 701 30 0 202 MAK0 13 2.3879 143.274 0.54 681 7il 0 202 MAKO 13 2.397 143.82 0.546 666 '90 0 202 MAkt, 13 2.4se 144.36 0.54 655 M 0 202 Matt 13 2.4175 145.05 J.69 644 385 ) 202 9K5 13 2.4319 145.914 0.8!4 633 .t03 0 202 MAKO 13 2.452 147.12 1.206 621 381 0 202 MAKO 13 2.4722 148.332 1.212 612 378 0 202 MAKO 13 2.5024 150.144 1.812 601 377 0 202 MAKO 13 2.5326 151.956 1.812 592 376 0 202 MAKO 14 2.5426 152.556 t.6 630 '39 1862300 220 MAKO 14 2.5526 153.156 0.6 663 400 1862300 220 MAKO 14 2.5626 153.756 0.6 689 409 1962300 220 MAKO 14 2.5726 154.356 0.6 7M 414 1862300 220 MAKO 14 2.5826 154.956 0.6 724 620 1962300 220 MAKO 14 2.5951 155.706 0.75 740 425 1862300 220 MAKO 14 2.6104 156.624 0.918 758 411 1862300 220 MAKO l 14 2.6307 157.842 1.218 777 439 1862300 220 MAKO 14 2.6511 159.0a 1.224 795 445 1862300 220 MAKO 14 2.6783 160.698 1.612 015

45) 1862300 220 MAKO 14 2.7054 162.324 1.626 833 460 1862300 220 MAKO l

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8WP4P-20667 (6 44) TABLE 1 PRESSURIZER TRANSIENT OATA (BASED ON t.5 EIPOSED SUNDtES) DELTA MAI PROSE HEAT FLUID MICR0 LOAD TIME TIME TIME TEMP TEMP Q TEMP FICHE STEP (HRS) (MIN) (MIN) (F) (F) (BTU /HR) (F) I 14 2.7326 163.956 1.632 S49 467 !!62300 220 MAKO 15 2.7413 164.478 0.522 919 457 0 220 MAKD 15 2.7501 165.006 0.529 791 449 0 220 MAKD 15 2.7605 165.63 0.624 766 442 0 220 MAKO 15 2.7709 166.254 0.624 749 438 0 220 MAKO 15 2.7813 166.878 0.624 735 434 0 220 MAKO 15 2.7924 167.544 0.666 723 432 0 220 MAKD 15 2.8086 168.516 0.972 709 429 0 220 MAKD 15 2.8269 169.600 1.092 697 426 0 220 MAKD 15 2.8501 171.006 1.398 684 424 0 220 MAKO 15 2.8791 172.746 1.74 672 422 0 220 MAKD 15 2.9131 174.786 2.04 660 420 0 220 MAKD 15 2.9534 177.324 2.538 649 419 0 220 MAKD 15 2.9978 179.869 2.544 640 419 0 220 MAKD 15 3.0402 192.412 2.544 633 4tB 0 220 MAKD 3.0826 184.956 2.544 627 418 0 220 MAKD 16 3.0909 105.454 0.499 664 430 1962300 220 MAKD 16 3.0993 185.958 0.504 694 441 1862300 220 MAKD 16 3.1076 186.456 0.499 719 449 1862300 220 MAKD 16 3.1159 186.954 0.498 737 454 1962300 220 MAKD 16 3.1243 187.458 0.504 752 459 1962300 220 MAKD 16 3.134 199.04 0.582 767 464 1962300 220 MAKO 16 3.1461 183.766 0.726 784-469 1862300 220 MAKD 16 3.1644 189.864 1.098 905 476 1862300 220 MAKD 16 3.1926 190.956 1.092 323 483 1962300 220 MAKO 17 3.1909 191.454 0.498 799 474 0 220 MAKD 17 3.19')3 191.959 0.504 774 466 0 220 'MAKD 17 3.2082 192.492 0.534 754 461 0 220 MAKO 17 3,211 193.02 0.529 739 457 0 220 MAKD 17 3.2259 193.554 0.534 728 454 0 220 MAKD 17 3.23 h 194.196 0.642 718 452 0 220 MAKD 17 3.2503 195.019 0.022 707 450 0 220 MAKD 11 3.2669 196.000 0.99 697 448 0 220 MAKD 17 3.298? 191.322 1.314 697 445 0 220 MAKD 17 3.3107 199.642 1.32 678 444 0 220 MAKD l' 3.3326 199.956 1.314 671 443 0 220 MAKD i PREPARED OV N OATE N [ f f N4 !h PAGE NO. 27 REVIEwt0 sy_ DATE U

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t.b -, -M T1. r.=:n n m. -.ww +- 2-TABLE 1 PRE 85URIZER TRANSIENT DATA (8ASED ON 1.5 EIPOSED BUNDLES) DELTA MAI PROBE HEAT FLUID MICR0 LDAD Tire TIME TIME TEMP TEMP Q TEMP FICHE STEP (HRS) (MIN) (MIN) (F) (F) (BTU /HR) (F) i 18 3.3409 200.454 0.498 704 454 1862300 220 MAKD 18 3.3493 200.958 0.504 733 464 1862300 220 MAKD 18 3.3585 201.51 0.552 758 472 1962300 220 MAKD 18 3.3678 202.068 0.558 778 47B 1962300 220 MAKD 18 3.377 202.62 0.552 793 484 1E52300 220 MAKD 18 3.3882 203.292 0.672 809 4B9 1862300 220 MAKD 18 3.403 204.18 0.888 827 495 1862300 220 MAKD 18 3.4178 205.068 0.888 842 500 1862300 220 MAKO 18 3.4326 205.956 0.888 856 505 1862300 220 MAKD 19 3.4423 206.538 0.582 829 496 0 220 MAKD 19 3.4521 207.126 0.588 803 488 0 220 MAKD 19 3.4618 207.708 0.582 783 482 0 220 MAKD 19 3.4715 208.29 0.582 768 478 0 220 MAKD 19 3.4812 208.872 0.582 757 476 0 220 MAKD 19 3.4926 209.556 0.684 74!. 473 0 220 MAKD l 19 3.5068 210.408 0.852 73 471 0 220 MAKD 19 3.525 211.68 1.272 723 468 0 220 MAKD 19

3. 9 93 212.958 1.278 713 467 0

220 MAKD 20 3.5525 213.51 0.552 746 479 1862300 220 MAKD 20 3.5676 214.056 0.546 776 489 1862300 220 MAKD 20 3.5773 214.638 0.582 801 497 1862300 220 MAKD l 20 3.587 215.22 0.582 819 503 1862300 220 MAKD l 20 3.5967 215.802 0.582 834 508 1862300 220 MAKD 20 3.6081 216.49,4 0.684 847 513 1862300 220 MAO 20 3.6236 217.416 0.9I 967 518 1862300 220 MKS 23 3.6418 118.508 1.092 824 525 1862300 220.MAKD 20 3.6645 219.87 1.362 903 532 1962300 220 MAKD 20 3.6872 221.232 1.362 919 538 1962300 220 MAKD 20 3.7I26 223.956 2.724 948 550 1962300 220 MAKD 21 3.7409 224.454 0.498 918 539 0 220 MAWH 21 3.7493 224.958 0.504 891 531 0 220 MAW l 21 3.7576 225.456 0.498 871 525 0 220 MAWH I 21 3.7659 225.954 0.498 855 522 0 220 MEH 22 3.7774 226.644 0.69 875 530 1962300 220 MNil 22 3.7E89 227.334 0.69 899 540 1862300 220 MAWH 22 3.8003 228.018 0.684 919 546 1962300 220 MAWH l PAEPAAED BY [ OATE N i!N PAGE NO. M REVIEWED BY DATE ---V_________.

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d M'."iids _ C - e.- - N. ...a TABLE 1 PRESS 1!RIZER TRANSIENT DATA (BASED CN 1.5 EIPOSED 81:NDLES) DELTA MAI PROSE HEAT FLUID MICR0 LOAD TIME TIME TIME TEMP TEMP 9 TEMP FICHE STEP (HRS) (MIN) (MIN) (F) (F) (BTU /HR) (F) 4 22 3.8118 228.708 0.69 934 552 1862300 220 MAWH 23 3.8211 229.266 0.558 910 544 0 220 MAWH 23 3.8304 229.824 0.558 886 536 0 220 MAWH 23 3.8396 230.376 0.552 867 530 0 220 MAWH 23 3.8489 230.934 0.558 852 527 0 220 MAWH 23 3.8582 231.492 0.558 840 $24 0 220 MAWH 23 3.8703 232.218 0.726 828 521 0 220 MAhH 23 3.8849 233.094 0.876 817 519 0 220 MAWH 23 3.9036 234.216 1.122 805 517 0 220 MAWH 23 3.9261 235.566 1.35 794 515 0 220 MAWH 23 3.956 237.36 ,1.794 781 513 0 220 MAWH 23 3.986 239.16 1.8 771 511 0 220 MAWH 23 4.0159 240.954 1.794 763 510 0 220 MAWH 24 4.0256 241.536 0.582 800 523 1962300 220 MAWH ^ 24 4.0354 242.124 0.588 832 534 1862300 220 MAWH 24 4.0451 242.706 0.582 856 542 1862300 220 MAWH 24 4.0548 243.288 0.582 876 548 1962300 220 MAWH 24 4.0646 243.876 0.588 891 553 1962300 220 MAWH 24 4.0743 244.458 0.582 905 558 1862300 220 MAWH 25 4.0831 244.986 0.528 885 551 0 220 MAIW 25 4.092 245.52 0.534 863 543 0 220 MAZW 25 4.1008 246.048 0.528 845 538 0 220 MAZW 25 4.1097 246.582 0.534 832 535 0 220 MAZW 25 4.1185 247.11 0.528 823 532 0 220 MAZW 25 4.1307 247.842 0.732 812 531 0 220 MAZW 25 4.1449 248.694 0.852 803 529 0 220 MAZW 25 4.1627 249.702 1.058 794 527 0 220 MAZW 25 4.1893 251.358 1.596 784 525 0 220 MAZW 25 4.2159 252.954 1.596 775 524 0 220 MAZW 26 4.2242 253.452 0.498 808 535 1962300 220 MAZW 26 4.2326 253.956 0.504 837 545 1962300 220 MAZW 26 4.2426 254.556 0.6 864 554 1962300 220 MAZW 26 4.2526 255.156 0.6 884 560 1862300 220 MAZW 26 4.2626 255.756 0.6 900 566 1962300 220 MAZW 26 4.2726 256.356 0.6 914 570 1962300 220 MilW 26 4.2826 256.956 0.6 926 574 1862300 220 MAZW PREPARED BY DATE [ Y / / REVIEWED BY OATE k PAGE NO. 2k u

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iV* me. 5 y A .M ^ ?. Wh... e .m -~~~~ R ?Z2 - + ~ir TABLE 1 PRESSURIZER TRANSIENT DATA (BASED 04 1.5 EIPOSED BUNDLES) DELTA MAI PROSE HEAT FLUID MICR0 LDAD TIME TIME TIME TEMP TEMP Q TEMP FICHE STEP (HRS) (MIN) (MIN) (F) (F) (BTU /HR) (F) 4 27 4.2916 257.496 0.54 905 566 0 220 MAZW 27 4.3007 258.042 0.546 882 559 0 220 MAZW 27 4.3097 258.582 0.54 864 554 0 220 MAZW 27 4.3187 259.122 0.54 850 550 0 220 MAZW 27 4.3277 259.662 0.54 840 548 0 220 MAZW 27 4.34 260.4 0.738 829 545 0 220 MAZW 27 4.3545 261.27 0.87 819 543 0 220 MAZW 27 4.3752 262.512 1.242 808 541 0 220 MAZW 27 4.4 264 1.488 798 539 0 220 MAZW 27 4.4331 265.986 1.986 788 538 0 220 MAZW 27 4.4662 267.972 1.986 779 536 0 220 MAZW 27 4.4993 269.958 1.986 773 536 0 220 MAZW 28 4.509 270.54 0.582 810 549 1862300 220 MAZW ^ 28 4.5187 271.122 0.582 842 560 1862300 220 MAZW 28 4.5284 271.704 0.582 868 568 1862300 220 MAZW 28 4.5382 272.292 0.$88 988 574 1862300 220 MAZW 4.5479 272.874 0.582 403 579 1862300 220 MAZW 23 4.5576 273.456 0.582 917 583 1862300 220 MAZW 1 PREPARED BY DATE 3/f Y r i b OATE k PAGE NO. 2 I REVIEWru 8Y O

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r q \\ POS-21036 3 (9-84) Babcock & WHcox GENERAL CALCULATIONS 3 MCDermott Company 32-1167603-00 Nuclear Power Division occ. i.o. Annendix At The results described in Section 9 are based on heat flux values assuming one and a half heater bundles located at the upper bundle location. A more realistic but still conservative heat flux value was calculated after most of this analysis was completed. The later value considered the actual location of the middle bundle with respect to the upper bundle and considered only 25 percent of the element: to be radiating heat on the sh ell. This later assumption of the pe rcent participation by the middle bundle was confirmed with Rancho Seco personnel as a result of the inspection performed on the middle bundle (i.e., one heater element deformed and four others discolored). In order to determine the effect of the change of heat flux values on the shell temperatures, a test case was run. The test case involved running the FE model to represent one hour of continuous heat input for both heat flux cases. The results of the test case are contained in microfiche runs: MGTK - 1.5 bundles 8 upper bundle location (Same as used in transient evaluation) MEE - More realistic case of 1 bundle at upper location and.25 bundles in middle locatfori i l l The maximum temperatures at the end of the one hour of heat flow are: 0 1079 F For Run MGTK 751 F For Run EEE Based on these v al ues, it is concluded that the 948 (calculated for the 0 transient) of Section 9.0 is conservative. Psc th/87 PtePAReo SY oAfa f N 37 Reviewen By oAre Pace wo. U

BwNP 20697 (6 35) Babcock & Wilcox DOCUMENT

SUMMARY

SHEET a Mcoermott company DOCUMENT IDENTIFIER 32-1167974-00 TITLF LOCAL HEATING OF PZR SHELL INSIDE CORNER PREPARED BY:- REVIEWED BY: NAM N NAMF S MM AN4 w.y SIGNATURV d-MM SIGNATURF AR X TITLFA//64d ^2<dQCVSbidnATE]lVfAE. TITLv E/VGR TIl I 9, 0 nATE TM STATEMENT: COST CENTER 8M REF. PAGE(S) REVIEWER INDEPENDENCE _ PURPOSE AND

SUMMARY

OF RESULTS:

Purpose:

On November 21, 1986, while heating up the pressurizer at Rancho Seco Nuclear Station, the water level in the pressurizer dropped below the level of the upper bundle. This resulted in an estimated increase in heater temperature to approximately 2200 F. 0 The radiant heat from these heaters increased the temperature of the shell. 4 For the duration of the event, the heaters were energized and de-energized in a cyclic manner. Also, the total number of heaters energized sometimes varied with the cycles. ~ The purpose of this calculation package is to determine the base metal maximum temperature resulting from the radiant heat of the exposed heater transient event. Results: i The maximum base metal temperature is conservatively calculated 0 to be 919 F and occurs at the inside corner region of the heater bundle shell opening. The maximum cladding temperature is conservatively calculated to 0 be 1002 F and occurs at inside corner. i l I l' THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT: C00E / VERSION / REV CODE / VERSION / REV AM5v.S/4./C PAGF / OF M

P05 2103G-3 (9 841 sancock a wucox GENERAL CALCULATIONS a MCDermott comDarty 32 1167e74-00 Nuclear Power Division occ. i.o. 1. PURPOSE The purpose of this calculation package is to determine the base metal maximum temperature resulting from the radiant heat of the exposed heater transient event. 2. BACKGROUND On November 21, 1986, while heating up the pressurizer at Rancho seco Ndelear station, the water level in the pressurizer dropped below the level of the upper bundle. This resulted in an estimated increase in heater temperature to approximately 2200 F. The radiant heat from these heaters increased the temperature of the shell. For the duration of the event, the heaters were energized and de-energized in a cycfic manner. Also, the total number of heaters energized sometimes varied with the cycles. Reference 1 contains the ' Time / Heat Output' data points relative to this " heater" transient. i 3. DESIGN INPUTS The definition of time vs. radiant heat output is taken from Reference 1 for a conservatively assumed 1.5 heater bundles. The shell material designation and geometry are taken f rom the original fabrication drawings (Reference 6 and 7). The radiant heat distribution on the inside surface of shell is taken from Reference 2. The heater sheath temperature profile adjacent to the shell thickness is taken from Reference 3. PREPARED SY DATE NAM Reviewso Sy DATE PAGE NQ.

r POS.21036-3 (9 84) Babcock & Wilcox GENERAL CALCULATlONS a Mcoermott comparty 32-1167974-00 Nuclear Power D...msson o o c. i.o. 4. ASSUMPTIONS This evaluation assumes that a maximum equivalent of 1.25 bundles was exposed. 5. COM PUTER PROGRAMS The general purpose analysis program.TNSYS, Reference 5, is used to perform the thermal analysis. 6. RESULTS The maximum base metal temperature is conservatively 0 calculated to be 919 F and occurs at the inside corner region of the heater bundle shell opening (Node 19, see Figure 5). The maximum cladding temperature is conservatively 0 ~ calculated to be 1002 F and occurs at inside corner (Node 1, see Figure 6). I i l l l l l PREPARED BY Dart A 3-2/9/E7 S Reviewed iY oAre

POS-21036 3 (944) Babcock & WHcox GENERAL CALCULATIONS 4 MCoermott company 32-1167974-00 Nuclear Power Division occ. i.o. 7. REFERENCES 1. 51-1167607-00 " Heater Element Time Intervals" 2. 32-1167978-00 "SMUD Pzr Heater Radiant Heat Energy Distribution" 3. 32-1167609-00 " Heater Element Temperature at Closure Region" 4. 32-1167603-00 "Pzr Shell Temperature Due to Radiant Heating" 5. B&W Technical Manual NPGD-TM-596, Rev. H, July, 1985, ANSYS, Rev. 4, Swanson Analysis Systems Inc., Houston, PA 6. B&W Drawing 135483E-7, " Pressurizer List of Materials" 7. B&W Drawing 135489E-4, " Heater Belt Details" PREPAREo sY oATE AN# neviewto av DAfe PAG E NO.

PDS 21036 3 (9 841 s.ncock a wiscox GENERAL CALCULATIONS a McDermott Cornpany e 32-11679t4-00 m Nuclear Power D...msson Do c. i.D. 8. CALCULATIONS An axisymmetric model of the pressurizer shell adjacent to the heater bundle opening was constructed. This model is shown in Figure 1. The mo~ del includes 12.5" thick base metal forging and the 3/16" nominal thickness stainless steel cladding on the interior surfaces. The attached microfiche of the computer run contains the nodal locations, element definitions and appropriate 0 0 material properties from 100 F to 1500 F. The loads are applied to the model in the form of nodal heat flow on a per radian basis. There are two sources of heat flow into the model: 1) radiant heat from the " active" heated length of the element (heater " active" length begins near inside shell surface and ~ extends escantially to opposite interior surface, i.e., approx. shell I.D.) and 2) radiant heat from heater sheath adjacent to shell wall thickness (this section of heater is " inactive" but has temperature rise due to axial conduction from active section). The heat flux resulting from the " active" and " inactive" sections of the heaters are applied to the appropriate surface nodes. The corner region of the model receives heat from both sources. The radiant heat f rom the " active" length of the heater bundle is absorbed by the shell as determined from the distribution of Reference 2. The distribution grid in Reference 2 is relative to the bundle centerline. PREPARED BY DATE REVIEWED sy DATE PAGE NO.

POS-21036-3 (9 84) san =ck a wucox GENERAL CALCULATIONS a McDermott company 32-1167974-00 Nuclear Power Da...ve. ion Doc. i.D. The evaluation herein uses the Ref. 2 relative distribution to determine " heat absorbed per node" from the upper bundle and, separately, the " heat absorbed per node" f rom 1/4 of the middle bundle. The two contributing values are then added to r, btain the total heat absorbed per node. The resulting values vs. " distance from bundle opening centerline" are shown in Figure 2. The radiant heat from the " inactive" length of the heater bundle is absorbed by the shell penetration surface. The temperature distribution of the " inactive" length of heater is determined in Reference 3. To approximate the heat absorbed by the penetration surface, the heat output of a 1" long section of " active" bundle (39 heaters) was multiplied by the ratio of: 4 temperature of 1" ldngth of " inactive" por'non R = ------------------------------------------- ----------- estimated temperature of the " active" portion (2200 F) The resulting values are then multiplied by the ratio of: " emitting area" (bundle outside surface) R = --------------------------------------------- " absorbing area" (penetration surface) The resulting values are plotted vs. " distance from inside corner" in Figure 3. The associated " inactive" heater sheath temperature is also included in Figure 3. l l l t PREPARED BY DATE A3. NAN 4 7 REVIEWED sy DATE PAGE NO.

= POS-21036-3 (9 84) Babcock & Wilcox GENERAL CALCULATlONS 4 McDermott comparty 32-1167974-00 Nuclear Power Division o c c. i.o. l 2 The heat flux intensity in " Btu /hr/in " is determinrA at each inside surface (shell and penetration) nod e. It is then multiplied by the " area per radian" attributed to the node (normally, " node radius x 1/2 length of each adjacent element"). It should be noted that the three corner region nodes absorb heat from both the " active" heater length and the " inactive" heat length. The " heat flow / radian" is put into the computer code. The cyclic operation of the heaters is evaluated by varying the heat flux in accordance with recorded data of Reference 1. The cycles are essentially as shown in Figure 4. The results of the computer run indicate that the maximum base metal temperature oc6urs at node 19 (corner base metal node). The temperature vs. time plots for this node is shown in Figure 5. _~ For information, the temperature vs. time curve for the maximum temperature node for the cladding is shown in Figure 6. Additionally, for reference only, a temperature vs. time plot for the node at the inside shell surface remote from the opening is provided in Figure 7. As an aid in visualizing the conduction of the heat throughout the model, Figure 8 provides a temperature contour plot at the transient time of maximum base metal (and cladding) temperature. The computer output microfiche of the computer run is located on the last page of this document. PReFAteD SY DATe 2 /87 7 PAGe NO. nevieweo av oAre

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FIGU RE 2--FLUX VS. DIST. FROM C.L. g( HORIZ. ALONG SHELL INSIDE SURF. 180.00 P 170.00 160.00 O h 150.00 m t l 5 140.00 d k 130.00 i ( \\ '120.00 y 110.00 CC hd w y 100.00 N~ 90.00 g g g i

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POS-21036 3 (9 84) Babcock & WHcox GENERAL CALCULATIONS 4 MCDermott comparty 32-1167974-00 Nuclear Power Division occ. i.o. S/GC,JS W $ FLUX US. DIST. FROM INSIDE CORMER 499 9aan O\\ 350. g .2299 \\ 399. Nm 1000 " 250. Z g.\\ \\ 299. .1499 g \\. \\ N s 4 2 159. \\\\ a \\ 'N a HEAT FLUX (BTU /HR/SQ IN SURF) 1999 ~ y w x 1a. N k 1 99 3 0 HEATER SHEATH TEMPERATURE W e 3 See I k 5 d (, i 8 4 is l'1 R El DIST. FROM INSIDE CORNER (INCHE3) M#/ PatPAnto eV OAft atviewto sY oAft PAGE NO.

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1. 1. 4 nEviEWED BY DATE PAGE NO.

BWNP 20697 (6 85) 9 Babcock & Wilcox DOCUMENT

SUMMARY

SHEET a McDermott company 32- / / h 7 60 -0O DOCUMENT IDENTIFIER mtc_Beo fe r 15 lem eaf Temp 1L%fwLe At_ClossLe_h egi wi PREPARED BY: REVIEWED BY:

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SUMMARY

OF RESULTS: /*u re as e-

be+etmine

+4e tempe ra fure along + he-un h ea+e.cl leng tf a & tAe p ressu citei be9 Ier elem enls q f tb e clo 5 u fe r eg lon for fbe SMWb un co ve te d h ee ler L u n dle. c a n eli+r o n. ~ 13esulfs Tle heeler elemen+ +empero fute. n ee r the dia h plefe app ro a c he.s F/> e am hien +p ey mtemp e ra fu re. ltsa 9=) s in in t h e.s f ro the.ja/ ole i f is Jes s fbgnaujoy/co abave a m blen f l m f pa e s-F=r 9 Femp e rg +u re. 5 e e. $ h 6 h C k o h [ c. E'eMj3ef4fVl~Q. f DO C-i THE FOLt0 WING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT: CODE / VERSION / REV CODE / VERSION / REV / b OF PAcr

r PDS 21036-3 (9 84) GENERAL CALCULATlONS saa.cac= a wuc== a McDermott company Nuclear Power Division ooc. i.o. 2 2 ~ /[b M O '-~ O O PUR Po S E tes +ing at (f en cbo Seco the. we fer b uring ! rag p e d leveI b e low rf e. p res s u riter 's c uppe c heg fer bundk. Previ ou s an,/ s i s CRef.t) in di e a le d t-fe h ea fed lengi,f a F tbe un c o ve r e el h un d le. m,y have r e a e. 4 e d o=. The p urp o.s e o f this c.e /c ulo ft o 27-o o r n is to de termin e the te mp e ro fure e/ang. the vn h ea fe el leng th a F th e. hea fer elem en fr a f t h e.

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M _hT P s p . N k y s u nheatec) heg t e d I eng th jeng th A#6 z/5-/e7 ...,A... .A,, RtyttWE. By oAft , AGE NO. II

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/r =. T /> e r m o I c.on elu c h vi+y k =. l3. +s a tv /n r -t=t

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/6 C P - / 2pl -2. N o (&. I 2. 2. S-c'/= L!C! W PnePARED BY DATE REVIEWED sy DATE P AG E 'N O. o

POS 21036 3 (9 84) sancock a wiscox GENERAL CALCULATIONS a McDermott company 3L-/ o O Nuclear Power Division occ. i.o. a h = Con vective he-o f fran s f er coe ffici en f h x A-13 tu /p r - i=t'

• t=

Al* f e, Tbelmol radiobion is if no f e d. O. b. = o r 6 6 in. R e. h. 2, p og e. S .E. D. : o 6 6 - 2. (c. /o 7) = 0, 4 4 6 in. A e. f. 2., g oge F l' = Pe ri<n e f e r P = 1r (o. 6 6) = t.o p s in. = o.t ra. 8 f +. d : _+IC([o 66) - (o 4-46[) : o. / 84 In ' : / 2 9/ X /o'A k6 l / //. / B 7 6 - / 3/15 - 80.3 7 5 -2.o -/S, 8 / LS-Re. f. + & S' t = // S 8 7 5 ro. = o 9 7 A-Ft. Y = T,. +- D; -5) co s h [m li. ~ x): fref.6,,aageci C.o 3b m L whe re. m = [ h P / tc A ~ m : [4 (0./ 718 /(/3.+F)( / 19/ X /o-3))' m: 6 3/ St l f = 2.S'o t- (2. u oa - 2.Co) Cobb{&.3/(o.??+-X).] l Lo Sh [ G 3/ (.o' ? 74-) ] > *J zA* ....A... .A,, .EVitWED.Y DATE . AGE NO. 1 [.

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SwNP 2069716-59 y ~; t,, u ' i' a ucc<rmott company Babcock &Wilcox DOCUMENT

SUMMARY

SHEET y ~ DOCUMENTIDENTIFIER 3 b //h ) Y O 'O TITLv PRh Con fac h Ten)rs e ra N(e bJif b }le n htr 2 le,rr e n f PREPARED BY: REVIEWED BY: ( NEPM.D

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e. l e in e,,./

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0. b. = 0 6 ? in.

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z. b. : a. % +b in.

N, d = 0 2 5 in. a.ss we d (m eas u re 5 km s ~ple) \\ 0 ; ?- 8 a sSum e d ( fro m n L \\ LJ ie q 9n d O f* cuing ) L = 0,83i~ jn. assumed ( se. ole'd a;F We v ldiegenc! d f 9 win {) --> c} 4--- ( + N o. l O tR. -/4-65S8 - 7 97 /?C / /, Alote,1 Art d tc, wing is oc, r i. D 6 rld's Record s Ce.n te r ,tc 3 l \\ _y_. So 'velu e s a re-. ass ...sa , c-- Pre ssuris e r fam i I v l l b,EC4 $ g $ $CYne$$ z A T Qa l 8 ) V {q, A s h. f-ts = Lose me +oi = s. en s~ in. (a rbitra r th i c lin e :,. ac%si thic irn e.s s is 6.18 75~ is. Ile5, + ) D = cliomefer o f /o co /i te d-re g ton = / 2. in. (ar6inar cham ele r as it is assume d on l y elem en+ 1s in e n fa c+ w it l, t h e sliett) y o n e-heater ...,4..o i r - M o,r, M7/87 W5 zh /M-3 Ib

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c. = re Tb ( b en s ; },',

Press urI ?-e r cla delin es noteri9/ aumber in mode / l 3o+ s, s, /._ o s l heferi,/ f pe_ a, 7 j;rspect t e S eien c e :. aie Tbe s :< m e a: used se>is. Pre s s u ti t e T E c, s e. /1 e_ te / l M9 feri9l n um b e r in me> del 2- /19 feri9/ typ e. : S A -S/ 6 6 r 7o R e.f. 5 - f+op e r ty le f eien t e s are flne s ame. a s u s eel a h o s e. N/d o.r. Z /7/87 CFS z/9 /O-8 o.r. ....~o.

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SUMMARY

SHEET a McDermott comparty DOCUMENT IDENTIFIER S 2-1167616-00 Tm r E4fSSWA/ZEA /rbWTff ELEMM7" ?dNd;d AC/?D PREPARED BY: REVIEWED BY: M [ b # NAM NAMF ..Jo e,; F. S u ev a @ NAMF 3# SIGNATURF SIGNATURF h- / 1 \\ g l l wtr_Ey&M OAT L 2/./ft? Tmy$upseuttoly E u calt ogrg *1,h N% i TM STATEMENT: COST CENTER M7 REF. PAGE(S) 6 REVIEWER INDEPENDENCE f PURPOSE AND

SUMMARY

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