ML20098F082

Affidavit of Jc Finneran in Support of Applicant Reply to Case Answer to Applicant 840618 Motion for Summary Disposition Re Local Displacements & Stresses.Certificate of Svc Encl

ML20098F082
Person / Time
Site:	Comanche Peak
Issue date:	09/28/1984
From:	Finneran J TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20098F077	List: ML20098F076 ML20098F082
References
OL, NUDOCS 8410020295
Download: ML20098F082 (24)

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UNITED STATES OF AMERICA 'Si DCT - A9 33 NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSI BOkR NEN.f.

s.- . . w In the Matter of )

) Docket Nos. 50-445 and TEXAS UTILITIES ELECTRIC ) 50-446 COMPANY, ET AL. )

) (Application for (Comanche Peak Steam Electric ) Operating Licenses)

Station, Units 1 and 2) )

AFFIDAVIT OF JOHN C. FINNERAN, JR. IN SUPPORT l OF APPLICANTS' REPLY TO CASE'S ANSWER TO l APPLICANTS' MOTION FOR

SUMMARY

DISPOSITION l REGARDING LOCAL DISPLACEMENTS AND STRESSES I, John C. Finneran, Jr., being first duly sworn hereby depose and state, as follows: I am the Project Pipe Support Engineer for the Comanche Peak Steam Electric Station. In this position I oversee the design work of all pipe support design organizations for Comanche Peak. A statement of my educational and professional qualifications was received into evidence as Applicants' Exhibit 142B.

Q. What is the purpose of this affidavit?

A. This affidavit provides information in support of Appli-cants' Reply to CASE's Answer to Applicants' Motion for Summary Disposition Regarding Consideration of Local Displacements and Stresses. I address below the arguments CASC presents in the affidavit of Mr. Doyle (" Affidavit").

CASE takes issue only with respect to Applicants first statement of material fact.

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Q. What is your response to CASE's first argument regarding Applicants' motion?

A. CASE disputes Applicants' statement in Attachment A to my original affidavit regarding the effect of neglecting air film insulation in the calculation of the temperature of the tube steel-(Affidavit at 3-4). It appears CASE misunder-stands Applicants' statement and the principles of air film insulation. CASE seems to believe that the " air film" which Applicants mentioned is located at the interface, or point of contact, netween the tube steel and the pipe. There is no air film at.the point of contact of the pipe and box frame. This phenomenon occurs over the remainder of the

. surface area of the box frame. Its insulating effect serves to reduce the rate of heat transfer from the frame to the surrounding atmosphere, thereby causing the frame to expand further and reduce the stress between the pipe and frame.

Thus, neglecting this effect as Applicants have done is conservative.

Further, for the situation CASE apparently envisions to exist regarding air film, a gap between the frame and the pipe would have to be present. However, were such a gap to exist, which it does not, the pipe would be able to expand through that gap before contacting the frame thereby reducing the ultimate stress between the pipe and the frame.

CASE apparently does not recognize this consideration.

Finally, I note that we have recently performed, at the

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request of the NRC Staff, a finite difference analysis of the temperature distribution within the box frame of this support. This analysis was provided to CASE with Appli-cants' letter to the NRC Staff, dated September 24, 1984. A copy of the results of that analysis is attached hereto as Attachment A. As demonstrated therein, Applicants' initial assumption for the-temperature distribution in the box frame was very conservative. Applicants originally assumen an average temperature within the frame of 203 F. The finite difference analysis found that the minimum temperature within the frame is actually 206 F. The average temperature in the frame is greater than 220 F. At this higher tempera-ture the frame will expand more than originally assumed and, thus, the stresses in the pipe and the frame will decrease.

Accordingly, Applicants' original simplifying assumption was conservative, as we indicated at that time.

Q. What is your reply to CASE's second point?

A. CASE contends that the temperature gradient in the tube steel will vary along the tube from that existing through the tube at the point of contact of the frame and the pipe (Affidavit at 4). However, CASE does not point to any particular effect it believes this varying tempeceture gradient will have on Applicants' analysis. Consequently, it is not possible to respond directly to CASE's argument.

It should be noted, nonetheless, that Applicants' finite L.

i difference analysis mentioned above demonstrated that the-temperature gradients along the tube are, in fact (as origi-

-nally assumed) nearly linear across the frame and along the length of the tube away from the point of contact between the frame and the pipe (Attachment A; sh. 11 of 11). Thus, although the gradients do vary, Applicants' assumption of linearity for taking an average temperature of the tube was reasonable and, in fact, conservative given the conclusion from the finite element analysis that the lowest temperature in the frame (206 F) is actually higher than the average temperature (203 F) originally assumed. Thus, the expansion of the frame will actually be greater than initially estimated.

Q. What is your response to CASE's third assertion?

A. CASE asserts that the expansion of the frame caKculated by g Applicants will actually be "far less" because of the ther-mal gradients (Affidavit at 4). As I have already noted, Applicants' original assessment was appropriate and very conservative, actually underestimating the expansion of the frame. CASE's assertion to the contrary is simply wrong.

CASE also claims that the thermal gradients within the box frame will give rise to differential expansion of the frame, creating internal thermal stresses (Affidavit at 4-5). The Board has already ruled that such internal thermal

stresses.need not be considered under the ASME Code

.(Memorandum and Order (Thermal Stress in Pipe Supports),

July'6, 1983).

What is your response to CASE's fourth argument?

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A. CASE'again asserts that the thermal gradients within the box frame are not linear (relying on CASE Exhibits 669B, Items 13E-13J) and, thus, stresses will be higher due to " direct bending . . . only as a result of thermal constraint" (Affi-davit at 5). In the.first instance, it is not possible to draw any meaningful conclusion by comparing CASE's exhibits with the support at issue here. Heat flow calculations involve many parameters and are highly dependent on config-

-uration, proximity to the pipe, number of and extent of contact points with the pipe, etc. None of the configura-tions in CASE's exhibits are similar to the support involved here. Finally, to the extent CASE again argues.that stresses resulting from " thermal constraint" need be con-sidered, as I already noted the Board previously ruled that such stresses need not be considered.

Q. What is your reply to CASE's final argument?

A. CASE's final assertion is that Applicants' employed an incorrect value for Young's Modulus in calculating the expansion of the frame (Affidavit at 5). CASE apparently assumed Applicants employed an AISC formula for calculating the coefficient of thermal expansion. However, because this support is an ASME support, Applicants utilized the value

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for the coefficient of thermal expansion set forth in Appen-dix I to Section III of the ASME Code. Applicants used the value set forth 'in Table I-50 (Attachment B) for the

. coefficient at 200 F (6.38 x 10-6) adjusted for the 203 F temperature assumed for the frame (6.387 x 10~0). Finally, it should be noted that although CASE apparently contends Applicants should have used the coefficient CASE derived, CASE does not acknowledge that to do so would be less conservative in that the expansion of the frame would be greater and, thus, lower stresses would be created in the frame and the pipe.

Q. Do you have any further comments regarding CASE's assertions?

A. To summarize my previous' comments, I note that none of CASE's arguments raised valid concerns. CASE has failed to point to any significant effect that should have been, but was not, considered in Applicants' analysis.

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Coef.

Mesevie3s ficient' 70 100 150 200 250 300 350 400 450 500 550 600 650 700 750 800 Ca. hon steel; Cesbon moty A 6 07 0.20 6.44 6 67 6.89 7.10 7.33 7.54 7.76 7.96 8.16 8.35 8.54 8.76 8 94 9.16 eiert: In.= cluomo steeti 8 6.01 6.13 6.25 % 6.49 6.60 6.71 6.82 6.92 7.02 7.12 7.23 7.33 7.44 7.54 7.65 vi m

tibenuou 3 C.) C o .0023 .0061 .00'39 A140 .0182 .0226 .0270 .0316 .0362 .0411 .0460 '.0511 .0563 .0616 .0670 O

Interme<tiete cheonie steels A 5.73 5.00 6.13 6.30 6.42 6.54 6.71 ' 6.85 7.03 7.16 7.35 7.47 7.60 7.75 7.90 8 02 o 4% Ce thenugh 9 Cel 8 5.73 5.79 532 6.04 6.12 6.19 6.27 6.34 6.42 6.50 6.58 6.66 6.73 630 6.88 6 96 Z C 0 .002; .0058 .0094 .0133 .0171 .0210 .0250 .0293 .0335 .0380 .0424 .0469 .0514 .0562 .0610 g

ti.uh .evume nteels A 5 24 5.34 5.53 5.72 5A7 6.05 6.21 6.36 6.50 6.66 6.80 6.94 7.01 7.08 7.21 7.36 2 112 Ce thenugh 11 Cel 8 5 24 6 29 5.40 5.50 558 5.66 5.74 5.81 5.89 5.96 6.05 6.13 G.20 6.26 6.33 G 39 ,1 C 0 .0020 .0053 .0086 .0121 .0156 .0}93 .0230 .0269 .0308 .0349 .0390 .0431 .0473 .0516 .0500 $

, g O Z

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• Austenitic stemiess steel A 9.11 9.21 9.39 9.50 9.66 9.73 9A7 9.9G 10.09 10.20 10.34 10.43 10.54 10.66 10.81 10.90

(IR Cr 8 Nil 8 9.11 9.16 9.25 9.34 9.41 9.47 9.53 9.59 9.65 9.70 9.7p 9.82 9 87 9.93 9.99 10 05 7 C 0 .0034 .0090 .0146 .0203 .0261

.0320 .0380 .0441 .0501 .0562 j.0624 .0687 .0751 .0815 .0880 2% Co.20 NI A 148 7.60 1.18 7.96 8.13 8.27 8.45 857 8.74 8.88 9.02 9.16 9.30 9.42 9 56 9.70 $

H 748 7.54 7.65 7.76 7.84 7.92 8.00 8.08 8.15 8.22 8.30 8.38 8.45 8.52 8 60 8 68 C 0 .0028 .0074 .0121 .0170 .0218 .0269 .0320 .0372 .0424 .0479 .0533 .0588 .0644 .0702 .0760 h'"

O Neth el Chmme lenn A 1 13 7.26 7.46 7.63 7.77 7.91 8.02 8.10 8.16 8.23 8.33 8.43 8.53 8.63 8.73 8 98 7 0 7.13 7.20 730 7.40 7.48 7.56 7.63 7.70 7.75 7.80 7.85 7.90 7.95 8.00 8.05 8 to Z C o .0026 .0070 .0115 .0161 .0209 .0256 >

.0305, .0353 .0402 .0452 .0502 .0553 .0605 .0657 .0710 A sum.num A 12 75 1262 13.12 13 52 13.80 14.06 14.34 14.67 14.95 15.24 15.49 15.79 ... ... .

G 12 25 12.39 12.67 12.90 13.12 13.28 13.44 13.60 13.75 13.90 14.05 14.20 ... ... . .

C 0 .0046 J123 .0200 .0283 .0366 .0453 .0539 .0628 .0717 .0810 .0903 . ..

Nu l t' ;

1 Coef hcient A is the instantanaous coef f.reent of thermal expension X 10' (inim/Fl. Coefficient 8 is the mean coefficient of thermal expansion X 10' lin.1in/F) in gomg r3 f..wn to i to nws.ree 1 temswsture. Cocthrient C is the lineer thermal expension (inift.) in going f rom 70 F to indicated temperature. *>

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[_ JYnC t-UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION _

BEFORE THE-ATOMIC SAFETY AND LICENSING BOARD k h yh 3 RANCH

.InLthe' Matter of )

. . )

TEXAS UTILITIES ELECTRIC ) Docket Nos. 50-445 and COMPANY, o_et _al . -

). 50-446 (Comanche 1 Peak. Steam Electric ) (Application for Station, Units 1 and 2) -) Operating Licenses)

. CERTIFICATd OF SERVICE

I hereby certify that copies of " Applicants' Reply to CASE's, Answer to Applicants' Motion for Summary Disposition Regarding

Local Displacement-and Stresses," in the above-captioned matter.

=

wasEserved'upon the following. persons by-express delivery (*),. or-

' deposit in the United States mail,.first class, postage prepaid,

.thisD28th day of September, 1984, or by hand delivery (**) on the 1st day of October, 1984.

m; ** Peter B.~Bloch, Esq. Chairman, Atomic Safety and-

^ Chairman,; Atomic Safety and Licensing Appeal Panel Licensing Board U.S. . Nuclear Regulatory U.S.-Nuclear Regulatory .

Commission.

, -Commission Washington, D.C. 20555

. Washington, D.C. 20555 Mr.. William L. Clements

• Dr.4 Walter-H.' Jordan _ Docketing & Service 1 Branch 881 West. Outer Drive U.S. Nuclear Regulatory:

10akLRidge, Tennessee .

37830 Commission Washington, D.C.- 20555

• Dr.-Kenneth A. McCollom s -Dean,' Division of. Engineering

' Architecture and Technology. **Stuart A. Treby, Esq.

z Oklahoma. State University Office of.the Executive Stillwater, Oklahoma 74074 Legal Director

'U.S. Nuclear Regulatory LMr.' John 1 Collins. Commission

. Regional Administrator, Washington,-D.C. 20555

, Region IV-

. U.S.; Nuclear Regulatory- Chairman,' Atomic Safety and Commission- ~ Licensing Board Panel

. '611;Ryan Plaza Drive 'U.S. Nuclear' Regulatory 4L  : Suite 1000 Commission Arlington,' Texas' -76011 Washington, D.C. 20555 j a:

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- g-Renea Hicks, Esq. *Mrs. Juanita Ellis Assistant Attorney General President, CASE Environmental. Protection 1426 South Polk Street Division Dallas, Texas 75224 P.O. Box 12548 Capitol Station- Ellen Ginsberg, Esquire Austin, Texas 78711_ Atomic Safety and Licensing Board Panel Lanny A.LSinkin U.S. Nuclear Regulatory 114 W. 7th Street Commission Suite 220 Washington, D.C. 20555 Austin, Texas 78701 i

i tt William A. Horin' cc: John W. Beck Robert Wooldridge, Esq.

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