ML19262C077

Forwards Addl Info Re Welds on Pressurizer Relief Piping Requested by NRC at 800116 Meeting.Stresses Produced by Draw Bead Technique Considered Equivalent to Stresses on Any Other Weld in Sys.Related Correspondence Encl

ML19262C077
Person / Time
Site:	Sequoyah
Issue date:	01/24/1980
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Rubenstein L Office of Nuclear Reactor Regulation
References
NUDOCS 8001280251
Download: ML19262C077 (12)

Text

,, 9 TENNESSEE VALLEY AUTHORITY CH ATTANOCGA, TENNESSEE 374o1 400 Chestnut Street Tower II January 24, 1980 Director of Nucler.r Reactor Regulation Attention: Mr. L. S. Rubenstein, Acting Chief Light Water Reactors Branch No. 4 Division of Project Management U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. R*2benstein:

In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 On January 16, 1980, a meeting was held at Sequoyah Nuclear Plant with NRC-NRR Consultant R. M. Gustafson and TVA employees to discuss welds on pressurizer relief piping. During this meeting, Mr. Gustafson requested additional information which was not available at the plant site. Enclosed is the requested information.

Very truly yours, TENNESSEE VALLEY AUTHORITY

', Vl dd(

. M. Mills, Manager Nuclear Regulation and Safety Enclosure 3 1816 039 f6A'h 8001280 l ,

An Eaual Occortunity Emcicyer

ADDITIONAL IllFORMATION ON PRESSURIZER RELIEF LINE DRAW BEAD ALIGiC4ENT UELDS A meeting was held on January 16, 1980, between Roy Gustafson of NRC-fiRR and several TVA design and construction personrel. The following information was provided to Mr. Gustafson concerning the draw bead alignment welds on the pressurizer relief line:

1. A drawing of the weld area.

2. The welding procedure and the prccedure qualification.

3. Results of the Strauss test performed on a mockup.

4. Westinghouse specifications on water chemistry.

5. Pipe bending procedure.

6. The UT baseline scan for each weld.

7. Certified material test report (CMTR) for the pipe.

8. Special instructions from Engineering Design for this particular weld bead alignment.

9. NDE results.

In addition, l'r. Gustafson requested information that was not available at the time of the meeting. The requested information is contained in the following discussion.

Circumstances Requiring Use of Draw Bead and Discussion of Stress Analysis During the hot functional test, a pipe support providing restraint in the lateral direction failed to slide as designed, restraining the pipe in the vertical direction. The restraint is located at joint 33 shown on the sketch in enclosure 1. A copy of the restraint design is shown m enclosure 2.

The maximum anticipated vertical movement at joint 33 during normal operation was anticipated to be g 2.87 inches assuming a worst case operating temperature of 653 F. The hot functignal test had proceeded to an operating temperature of approximately 550 F at the time of discovery of the bound up support. The U-bolt which restrained the pipe in the vertical direction was deflected approximately one inch vertically.

Inordertodeterminethestresslevelsdugtotheboundsupport, an analysis was run with the piping at 550 F and a vertical restraint installed at joint 33. The vertical restraint was free for the one-inch vertical movement simulating the one-inch defermation of the U-bolt.

The stress levels for the joints shown in enclosure 1 are tabulated in enclosure 3. These stress levels are below the ASME,Section III allowablestressfornonrepeatedstressesasdefinegbyNC-3611.2(f).

That allowable stress for_A-376T316' is 60,000 lb/in . Pressurizer relief nozzle loads for this anomaly load case were forwarded to Westinghouse for review by enclJsure 4 and Were approved by enclosure 5.

Enclosure 6 gives maximum stress at node 13A during plant operation for occasional loads. Node 13A is within five inches of both draw' beads.

1816 040

Residual Stresses 'D }b Residual stresses are considered to be no 91 . than the stresses in a repair to base metal or in any other weld in the systi.m. The natur2 of these stresses at the inside diameter (id) induced by welding are considered to be compressive due to the technique ,used and conseguently will not adversely affect the material's susceptability toliitEes's corrosion cracking (IGSCC). Compressive stresses are known to have a mitigating effect on IGSCC; thus, we do not have stresses which can cause IGSCC.

~

Heat Input Calculation for Draw Bead Repair

1. Maximum heat input used on the preproduction mockup which passed a Strauss test.

Amps = 160A Volts = 14V Travel Speed = 3/4 in/ min = TS Heat input per irch = Amps X Volts X 60 Travel Speed in/ min

= 14V X 160A X 60

, 0.75 in/ min X 1000

= 179.2 kilojoules

2. Actual heat input used for production welding.

Amps = P'M Volts = 1V TS = 2 in/ min Heat input per inch = IlV X 90A X 60 2 in/ min X 1000

= 29.7 kilojoules Thus, it can be seen that the actual heat input for each draw bead is well within considered acceptable limits.

Anticipated Oxygen Content Area of concern is located in the 6-inch, schedule 160, vertical pi run leading to the pressurizer relief valve at an elevation approxi aly levelwithtgetopofthepresgurizer. The environment is saturateu steam at 650 F and 2485 lb/in 1816'041~

Based on the best information available to us from Westinghouse and operating utilities:

1. f taximum oxygen content in the reactor coolant gater is controlled to less than 0.1 p/m at temperatures above 180 F by scavenging with hydrazine.

2. During power operation, the residual oxygen concentration will not exceed 0.005 p/m.

3. The highest calculated oxygen concentration expected in the steam is less than 0.2 p/m.

4. EPRI information gives 6 p/m as the threshold value below which IGSCC will not occur in 316 stainless steel (reference GE report flo, flEDC-23750-6 dated flovember 1979, " Alternate Alloy for BWR Pipe Applications, Third Semiannual Progress Report."

It may therefore be concluded that the oxygen environment is not sufficient to produce IGSCC.

Summary Based on the foregoing discussion and the information g'.ven to !!r.

Gustafson at the Sequoyah meeting, the following conclusions may be reached:

1. Intergranular stress corrosion cracking (IGSCC) will not occur because:

a. Satisfactory results of an ASTM A262, Practice E test, on a mockup of a worst case situation indicates that the material (316 stainless steel in the existing condition) is not susceptable to IGSCC.

b. Residual stresses produced in the weld area will be compressive and, consequently, will not contribute to IGSCC.

c. Environment for IGSCC does not exist due to low oxygen concen-tration.

2. Stresses produced by the draw bead technique are considered to be equivalent to those in any other weld in the system and do not adversely af fect the Sequoyah piping analysis.

TVA concludes that the subject condition will not compromise safe operation of the plant. Furthermore, we have met or exceeded all licensing and code commitments for Sequoyah.

1816 042

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Enclosure 3 Table of Stress Levels Joint Stress A11cudble Stret:s 32 38,215 60,000 33 h1,3c0 60, coo 35 13,283 60,000 38 27,033 60,000 3BA 23,648 60,000 19 24,734 60,000 40 17,064 60,000 8

181(i 047

F_wclostast 4

',/./ TENNESSEE VALLEY AUTHORITY D seioxvittx. Tensi.csr.c 37<,o:: ,

W10Cl26,400 Comerce Avenue

}Dp@p u h flay 30,1979

.s MEB '790529 12O Ucstinghouse Electric Corporation Past Of fice Box 355 Pittsburgh, Pennsylvania 15230

.Atteation: Mr. ii. A. Siano Gentleman:

SEQUO/Att I UCLEAR PLNIT

!!UCLEAR STEAM SUPPLY SYSTEMS CCi:TPACT 68C60-91934 LETTER I:0. 6349 fiOZ7.LE LOADS APPLIED TO '

UilIT 1 PRESSURIZER RELIEF Lit 1E f!0ZZLE (50145-01) -

fl2M-2-6(CU)

During hot functien21 testing at Sequoyah one of the supports on the pressurizer relief piping seized and would not permit free movemant of the pip 2; therefora, sec.e yielding occurred in the piping. He have calculated moments and forces for the pressurizer nozzle for the temperature trcnsient which resulted in tbn band pipe. The pipe was assumed to act clastically; therefore, we believe that tinse loads are conservative.

Please review for acceptability the following ncazle loads which are in local ccordinates.

Fy(l.bs) Fz(1.he.) th(F t-1.bs ) My( F t-1.bs ) Mz(Ft-Lbs)

Fx(t.bs)

-20,357 858 -13,664

-442 -16,302 993 Your expedient reply will be appreciated.

Very truly yours, TEf!i!ESSEE VALLEY AUTHORITY Oririn11 sifaci! Uy 1.. II. Chin D. ft. Patterson, Chief I'.cchanical Engineering Branch cc: fir. R. E. Lyman U dY 1816 048

. " An Eriori opportunity rmployer

. . . . . .' ~

- - Endow .5 ,. f?

7 ;re r 'W i" TVA-7.495.-

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45d. d L 1,6 ~ ~ ~ le.c- .?

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lestine,hcuse Watet Rch'cibtl F B'13 0613 5 6 6

• cor355 Fitt$N!,h Pecc.sytGia 15E0 if

.lectric Corporation Divisic!13  :!

Dc P "  %

U""" 4' I979 D D I TVA Contract fio. 58CGO-91937,

.t- g ,

b u 7[' df IVIT-ST-312 4

~L. J S.O. TVA/T31-130 g

)!r.D.R.Patterson, Chief -

!!cchanical En0 incering Branch '

Ref.: 1) Letter No. 6349. l TE!!!1ESSEE VALLEY AUTF.0RITY ' I 400 Commerce Avenue, '!10 C126 i f

l'noxville, Tennessee 37902 9

~ , t,

' i.I

Dear !!r. Pattersen:

j(i j

~

TENNESSEE VALLEY AUTHORITY SEQUDYAH !!UCLEAR PLAT!T  !

UllIT l' UMBERS 1 A:iD 2 j i

Loads Applied to Unit 1 Pressurizer Relief !!ozzle_ l The loads for the Unit 1 pressurizer relief nozzle The. presented loads in the above 'j referenced letter have been evaluated and are acceptable.

resulted frcm a seized relief pipe support during hot functional testing. ,;

for the evaluation the loads were compared with the normal and upsetIt was assu it condition allowables for primary plus secondary stresses.that th the fatigue lite of the nozzle will not be effected.

If you have any. questions concerning the evaluation, please contact me.  ;

Very truly yours, '

j WESTINGHOUSE ELECTRIC CORPORATION ,

- 6

11. A. SianosManager

/p & l f ' i g y,g 3979 Tennessee Valley Authority i

Projects .

^

05I^" lSlpUiES%!ygph M, D. R. Patterson - 3L .EEy. W6C({cC.g l l g g CE" *SC 'uc.< i i , , ,

cc: R. E. Lyman - lL ' i F. E. Rolsten - ll Eco l '

C. E. 11rever - 1L L.11. Ilills - ll Ut FoOnen l

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-- hM Urorrrm t4 2.M Q

EfiCLOSURE 6

?!0DE 13A 1303 STRESSES fiominal Stresses lb/in 2

1. Blowdown 238

2. Gravity (DW) 159.5

3. Abnonnal Thermal W/PRT 1419.5)

) Use worst

4. flormal Thermal 1607.1) thermal and

) cold spring

5. Cold Springing W/PRT 2225.6)

)

6. Startup Thermal flode W/PRT 2446.4)

7. OBEXY: Loop A tlodes 1 to 17 268.3)

8. OBEYZ: Loop A flodes 1 to 17 803.9

9. Pressure: Stress 0 2485 lb/in2design 3,943 lb/in 2

Intensification factor is 1.8 for butt weld.

Sum of all stresses for the above load cases:

2 238 + 160 + 2226 + 2447 + 804 + 3943 = 9818 lb/in nominal 9818 X 1.8 SIF = 17,672 lb/in 2 Allowable = 1.8 Sh for occasfocal loads 2

Sh for A376 TP 316 at 650 F: '6,700 lb/in Allowable = 1.8 X 16,700 1b/in 2 2

= 30,240 lb/in and stresses in this area are acceptable.

1816 050