ML18051A997

From kanterella
Jump to navigation Jump to search
Evaluation of Auxiliary Feedwater Piping for Postulated Water Hammer Event
ML18051A997
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/19/1984
From: Patricia Anderson
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:
Shared Package
ML18051A993 List:
References
NUDOCS 8407110396
Download: ML18051A997 (7)
v • d • e


Text

'.

P~POWER L..5 SYSTEMS NUCLEAR POWER SYSTEMS COMBUSTION ENGINEER ING, INC.

COMPONENTS ENGINEERING Chattanooga, Tennessee EVALUATION OF PALISADES AUXILIARY FEEDWATER PIPING FOR A POSTULATED WATER HAMMER EVENT SS-801 2966-B CALCULATION NO.

CONTRACT NO.

PALISADES STEAM GENERATOR CUSTOMER COMPONENT

~ t. a}!~µ~

Princieal Engineer 7'-1'1-<ffl PREPARED TITLE DATE

.cs:LL Principal Engineer 4-11-ft-CHECKED TITLE DATE (Full Review)

@1.-

.:/-- /'} - ;*~

~~

~~. Manager

( REVTEWED TITLE DATE APPROVED TITLE DATE

(~-on-~~~;;-:--~~---~

I 8407110396 840709 l

I PPDR ADOCK 05000255 PDR

*.n*.ijS..S** ~*

qs.;,;z;4J!

1?44?4¥>.

AA.*.

  • ..#.3 i"l -9.G@,-

P.2J4'!¥ tl.IPQti!.>;?.?.f I.

. Q..Lt.,-...* -

I 5.

0

.~

_,?.4.,

s *-.>

Attachnent ') *

/1 /

/;.~.~,.~ ~-/1-i; COMBUSTION ENGINEERING, INC..

f:r:.,.,.Hf.O

  • 0 "n:

ChattanoogJ Nuclear Operations

___;s;_H...;;;c~ET.
-__:/ __

0 _,,--::1"":::;..._ _ _,

J.~~r

  • 4-* 1 '*~?-I" **COMPONENT ENGINEERING CALC.NO. sr-a01 CHIECt<ED DATIC I CONTRACT NO.

2CJ(,,(,. 13 TITLE SUtff1ARY AND CONCLUSIONS The Palisades steam generator auxiliary feedwater pip)ng is evaluated for a postulated water hammer event.

The ana1ysis addresses the axial stress resulting fro~ a pressure pulse of 4000 psi la5ting less than 0.001 sec.

The predicted stress. at the minimum cross-section is 31 ksi which slightly exceeds the minimum yield stress of 27.5 ksi at 532°F.

This stress is significantly below the ultimate tensile stress of 60 ksi at temperature.

In view of the ductility of the carbon steel material, the stress of 31 ksi (52% of Su) is considered to be well below a damaging stress level.

A fatigue evaluation of 25 occurrences of the water hammer event indicates a negligible fatigue usage factor.

REV.

DATE I BV CHECK REV.

DATE BV CHECK REV.

DATE BV CHECK I

..)

}.)-

(

I

/J. L t,,t~L-~tt. 4*1'/*i'A, COMBUSTION ENGINEERING, INC.

11R1:11ARll!:D oAn i Chattanoog;i Nuclear Operations SHl:ll!:T CAl.C. NO.

<' r-B /J 1 d*}f:;;~f 4-~~~*}'LI COMPONENT ENGINEERING CONT.. ACT NO.

2'1 /_p ~ -13 TITLE REV.

DATE INTRODUCTION The purpose of this report is to evaluate a section of the.

Palisades auxiliary feedwater piping for loads resulting from a postulated water hammer event.

The piping section of concern consists of the horizontal run extending from the auxiliary nozzle to the first downturning elbow external to the generator.

A water hammer event is postulated -to produce a pressure pulse of 4000 psi in the horizontal pipe run.

This analysis considers the stresses resulting from the 4000 psi pressure pulse assuming that the pipe and welds are in a virgin condition. Duration of the pulse is 0.00083 sec.

BV CHECK REV.

DATE av CHECK REV.

DATE av CHECK

"!l!-2?,U- -

.....e:s

. p. l.

1

~.*

  • ~--*

r19i;:; 2*.'. ;se-0.....ss. u.c:cs.-

a; #Ja.,:s: s:z..

..,Q ¥.

. es.c q,.... : z

... ae o.

(

:----,----------:-1---- --------i

  • .i-p L. /t,f,.U'-~>"

f,.1'/ l'/. COMBUSTION ENGINEERING, INC

~I _:r~":.:1::....:.""'-:-H-1:_0 _____

0 "'-:T-11:-::-:-11 Chattanooga Nu c I car 0 per at ions SHEET

..3

. 0,. G, c1<Lc.No. sr-_qo1

~/!::::~' '~!:! 4-1 COMPONENT ENGINEERING CONTRACT NO. /q{,, ~-I?

TITLE REV.

DATE GEOMETRY AND MATERIAL PROPERTIES The minirnu~ cross-section of the piping occurs at the piping to nozzle l'leld.

For the minimum section Ri = 2.139 11 {max)

II t =.236 {min}

Amin = 3.35 in2 For the SA-106 Gr. B material at 532°F the ASME Code {Ref. 1) allowables are BY Sy = 27. 5 ks i *0 vSu =*60 ksi CHECK REV.

DATE BY I

15. [ l 5, CHECK REV.

DATE BY P*U

.,...... z...-www.--; ______

.,...,~~-r

..... WW.fl\\WSC4i 4 WCWWWWW44WWWCl CHECK

TITLE

. -)

-Y* i1' 1*~~

Attachmen~

EVALUATION OF WATER HAMMER LOAD Reference 2 describes the postulated water hammer event and presents the resulting pressure pulse.

"W!*-=-..

"°')

'l. ~&E"C'..

I it: *7H&i

~

~

~- I~

l"--* --..

t

~

---*a-

2.

I~

  • ,1 The short duration pulse results in an axial load "t...

I,*

2... ":

C......._._ -

"-f' _,

I

\\ Y\\

/T ~.:i. C.'?. + 0,01_,)

I

---=-*

IA.~lA\\M..l)W\\

C,..oS').-~C-!i;?o.A F = PA p = Peak Pressure -. 4000 psi 2

in2 A = Area of Pipe = -:rR = 12.97

.*.. ii... C'.

Considering the load to be sudden1y applied and applying a

...... ~-.,~~}"" dyna~ic amplification factor of 2 results in an equivalent

~, :

stat l c 1 oa d 11 s

~,) '>

REV.

DA'l"E llf,:>1

\\

F5 = 2F = 2(4000)(12.97) = 104 kips The axial membrane stress at the minimum cross-section is

! ! ;~/ s. 7. \\~ = -~.. ~.

  • '--~ *,

S = (5/Amin = 104/3.25 = 31 ksi This stress slightly exceeds the yield stress of 27.5 ksi, but is significantly below the ultimate stress of 60 ksi at temperature.

In view of the ductility of the carbon steel material, the stress level of 31 ksi (52~-; of Su) is considered to be well below a damaging stress level.

ASME code rules for a fa~lted event, for example, permit a membrane stress of 703

  • of Su with an adequate margin of safety.

BY CHECK REV.

DATE BY CHECK REV.

DATE BY CHECK

=-====----___::;:===-----=======:::::::::========-r1 --=:..====.. __

_..:__:.:_1

"° >

-: *.* *JCr;? L..J,...fcµ,,.

41-lf,~;',COMBUSTION ENGINEERING. INC. :-------- l I pnr;,.,.Rr:o 0 ""c:

Chattanooga Nuclear Operations 9Ht:c:T S'

o,.

~

(

TITLE REV.

DATE CALC:.NO.

SS-9~1 CONTRACT NO.

2 9(,, 6 - tJ COMPONENT ENGINEERING DATii FATIGUE EVALUATION

-7() L.::::1 A conservative stress concentration factor of 4 applied to the 31 ksi stress results in an alternating stress of 62 ksi.

Using the fatigue curves of Reference l, the correspon-ding allowable number of cycles is approximately 2000.* For a few cycles, for example 25 occurrecnes, the cumulative usage factor u =.0125 is negligible and fatigue damage is of no concern

  • BY

' ~

\\ *'.

\\ *..;->-

..,. ;N'*

CHECK REV.

DATE

  • 1
  • ~1.-o~

. _)...

f](!..ieil~

('"!

BY CHECK REV.

DATE

.,.,)

/..L ~ i,il***I BY CHECK

-*~--------A-4_q __ _.. __ ~*--~~--~--~------_.,.--------------~~----*----------------......,,_,_,.;. ______ ~...,~

r

.:>'* I I

I

/. L. t:-~t:k~

~-l~*?l COMBUSTION ENGINEERING, 'INC

  • 1~~---------~-------------___J p"l:P'A AC D DATE Chattanooga Nuclear Operations SHEET CH~~~~, 4-*t1-i4-COMPONENT ENGINEERING CATI:

CONTRACT NO. '? tf(,,6 -11 cALc. No.

sr-1J111 TITLE REV.

DATE REFERENCES

1.

ASftE B&PV Code,Section III for Nuclear Vessels and Addenda through Summer 1983.

2.

CE Report 2966-PSAE-001, "Evaluation of Water Hammer within Steam Generator Feed Pipe", A. J. Sowers.

BY CHECK REV.

DATE BY CHECK REV.

DATE BY CHECK

~-...........___._.. ________________

.~~---~~-------------.. --:-0-*--*-........... -.p*..

,,,,,, ___ _

Retrieved from "https://kanterella.com/w/index.php?title=ML18051A997&oldid=5023348"