ML18347A689

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Providing Corrections to Allowable Tube Wall Degradation Analysis, Submitted on 2/2/1976
ML18347A689
Person / Time
Site: Palisades 
Issue date: 03/22/1976
From: Bixel D
Consumers Power Co
To: Purple R
Office of Nuclear Reactor Regulation
References
Download: ML18347A689 (14)
v • d • e


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consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

  • Area Code 517 788-0550 March 22, 1976

~eguf atory Docket File Director of Nuclear Reactor Regulation Att:

Mr Robert A. Purple, Chief Operating Reactor Branch No 1 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT -

CORRECTIONS TO ALLOWABLE TUBE WALL DEGRADATION ANALYSIS Our letter of February 12, 1976 transmitted a request titled "Analysis To Determine Allowable Tube Wall.Degradation for Palisades Steam Generators."

Following submission of this report, a number of errors have been observed.

The following pages have been revised correcting these errors:

Title Page Sheet 5 Sheet 6 Figure A.5 Figure A.6 Figure A.20 Figure B.4 Figure B.5

-The border has been marked where changes were made and the corrected pages are attached.

?Lq;f2t~

"7 * -

_,.f-rr_

David A. Bixel Assistant Nuclear CC:

JGKeppler, USNRC 2957

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.NUCLEAR POWER SYSTEMS COMBUSTION ENGINEERING, INC.

COMPONENTS ENGINEER ING Chattanooga, Tennessee AANALYSIS TO DETERMINE ALLOWABLE TUBE WALL DEGRADATION FOR PALISADES STEAM GENERATORS P. L..Anderson J. w. Bass

w. Q. Gurley J. w. Hiestarid J. P. Houstrup D. s. Cassell
w. J. Heilker F. P. Hill, Jr.

January 29, 1976 Revision 1, March 5, 1976 11;*21105

COMBUSTION ENGl-ERING, INC.

l

.A r--

  • 5 SHEET~--'=-~-OF~~~~-

DESCRIPTION PALISADES STEAM GENERATOR Rev. i*

~-------*

4.. DEVELOPMENT OF LOADS ON TUBES FOR LOCA AN:O SSE_

(Cont ~ d)

Here f is the friction factor (0.011 from the Moody dia~*

gram 14 for a Reynolds 1 Number of. 964*x 10 6,

. W the mass.'**.~

  • ~... *
      • ~..... :.

.-.1_-:_**_

. *--~

flow rate per tube (lbm/sec) and. v the specific volume*--.

(ft 3 /lbm) in flowpath 42, and D the tube diameter.

Mul""'." * ::.*.* '~

  • /

tiplication by the horizontal length between the ascend-ing and descending tube legs yields the total friction

. force or drag *. on that section of the. tube.

The magnitude of. ttie.)1orizontal component of the. centri-fugal force is given by Fc(t) =

This* force was computed for each 90° bend and the alge-braic sum applied to the t~be.

These computations are summarized in Figure B.4.

\\

A parametric study was performed in order to identify a

11 worst case" in terms of the horizontal loading on the bend region of a critical tube row.

Possible break loca~

tions and.areas, and break opening times were chosen according to company standards.1~

Except where other-wise noted, all results shown are for tube row 114~..

Results for different break types are summarized in Fig-ure B. 5, where it is seen that the most severe loading **- **:

occurs for a double ended guillotine break in the \\:!Old_.. __ :

leg, downstream of the generator.

A comparison of the i

effect of such parameters as tube row (horizontal span~-~-~-*-~~-*

length), number of tubes, and break opening time upon * ***

results for the cold leg guillotine break are shown in *:.

'Figure B.6.

Here 6Pmax is seen to increase with tube row and decrease with both the number of functioning tubes and the break opening time.

From this param~tric study, the base case for detailed structural analysis was taken to be as follows:

cold leg guillotine break

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COMBU\\STI. ENGINEERING, INC.

' 'SH EET-*--~---OF --------

DESCRIPTION PALISADES STEAM GENERATOR

"\\..

Rev. 1

4.
  • DEVELOPMENT OF LOADS ON TUBES FOR LOCA AND SSE (Cont,-d). :

'-:~-~ 7:T:f.. -

tube row 114

.. -_:~::;L -~~~: ~;:.:;.~~~;

..* ~~!;kt~~ =~ing time o. olo_ se~ s..* : ;

.. ~ ~g~'t=):~~

The absolute pressue history du)'.'.ing the transient for :\\;:~~~*.:.!.\\?\\' *'.'..:..;,~:t.>!L.

Nodes 37 and 42, the nodes in the two 90° bends of* tube row 114, are *Shown in Figure B.7 and the relative pres-

. sure different!e'actirig.between.them is shown in Figure

  • B.8.

The maximy.m _.difference is 185 psi.

The ~orrespond ing pressure force/'tlfe fluid friction and centrifugal force :histories are shown in Figure B.9.

The algebraic summation of these component forces to produce the net

~ LOCA induced hydraulic loading *on the horizontal portion

  • of the tube is also presented in Figure B. 9. -. The maximum.

resultant loading is 56.0 lb.

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LOCA iJ1.s Pt. AC' /VIENT 1-/1 s TORY X

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LOCA.

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0/~C'CTION 13 Tl Mc

.20

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ALLOWABLE STRESS FOR TUBE MATERIAL MILL TEST REPORT NUMBER OF SAMPLES ULTIMATE TENSILE (RT)

NO. BELOW

% BELOW MINIMUM 90 KSI 90 KSI VALUE A-UNIT SAWHILL 278*

1 0.4 88.0 TUBULAR PRODUCTS*

B-UNIT

  • PACIFIC 603 7

1.1 87.5 TUBE COMPANY TOTAL 881 8

0.9 87.5 BASED ON CURVES FROM:

NUCLEAR SYSTEMS MATERIALS HANDBOOK FOR OPERATING TEMPERATURE OF 6000F Su = 80.0 KSI FROM SECTION III ASME CODE:

Sm= 23.3 KSI AND Sy_= 27.9 KS!, 6oo°F FROM APPENDIX F TO SECTION III FOR FAULTED CONDITIONS:

ALLOWABLE. SMEMB =.7 Su = 2. 4 Sm = 56 *KSI.

ALLOWABLE SMEMB +BEND = f'8 (SMEMB) = 1.44(56) =. 80.6 KSI WHERE f' IS THE SHAPE FACTOR FROM FIG. A.21 s

A.?

EVALUATION PER NRC STAFF (KNIGHT'S) CRITERIA

1.

NORMAL OPERATION a< Sy.= 27.9* ksii 6oo°F 6P Ri t

r - Sy - 0.5(P1+P2)

2.

NORMAL OPERATION 3a < Su ::: 80.0 ksi, 6oo°F t

. =

3 6P Ri r

Su - o.. 5(P1+P2)

3.

STEAMLINE BREAK a <. 7 Su = 56. o ks i, ~_go°F 6P R*

tr =

(

)

. 7Su- 0. 5 P1+P2 SPECIFICATION OPERATING CONDITIONS

1. 38 (. 32 7) tr =

(

)

27.9 - 0.5 2.92 tr = 0.017 P1 = 2150 PSI % Allow. Degradation I

P2 = 770 PSI 6P = 1380 PSI

% =.048 -

.017

.048

% = 64 tr = 0.017

/

% Allow. Degradation

% =.048 -

.017

.048

% = 64 2.15 (.327) tr= 56.0 - 0.5(2.15) tr = 0.013

% Allow. Degradation

% =.048 -

013

.048

% = 73

~-----------+---------*-~-- ------**-*-*~*---------*

TODAY'S OPERATING CONDITIONS P1 = 1850 PSI P2 = 600 PSI 1.25 (.327) tr - 27.9 - 0.5(2.45) tr = 0.015

% Allow. D~gradation

% =.048 -

.015

.048 tr= 3(1.25)(.327) 80.0 - 0.5(2.45) tr = 0.016

% Allow. Degradation

.048 -

.016

.048 tr=

1.85 (.327) 56.0 - 0.5(1.85) tr = 0.011.

% Allqw. Degradation

% =.048 -

.011

.048 6P = 1250 PSI % = 68

% = 66

% = 77 I

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PRIMARY WATER IN LET 40

  • 1¥1 39~

45 36

---PRr~rKRY"WATE OUTLET.

28 FIGURE B.3:FL.ASH STEAM GEf'.l:::RATOR DET:\\!L

I

  • ..,.:.. r*

. *:.; >:~...

~

I FIGURE B.4:

FNET Fp*-FF-(Fc -Fcx2) *

~

XI FNET= 60.8-3.5-1.2= 5 6. l L 8 F:

h NET

/

TUBE SUPPORTS

/.,()

/

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I Fcx1.

FLUID FORCES ACTING ON TUBE I

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FIGURE B.5 PALISADES STEAM GENERATOR COMPARISON OF POSTULATED LOCA BREAKS DURATION OF AREA B.O.T.

6 Pmax 6 PULSE TYPE OF BREAK IN2 SEC X 103 psi (SEC)

COLD LEG

~*

A)

GUILLOTINE 707..

.. :.LQ 185 0.0296 B)

SLOT 530 5.1 103 0.0l~2o*

HOT LEG A)

.. GUILLOTINE 425 15

-153 0.0258 B)

SLOT 812 7.5

-130 0.0256 Rev. 1 AREA OF

6. PULSE (LB-SEC) 0.9189 0.7270

-0.6630 I

-0. 5588

FIGURE B.6

  • PARAMETRIC S~UDY OF LOCA LOADINQ DURATION OF

'AREA OF e

6Pmax 6 PULSE 6 PULSE PARAMETER IDEN.

(psi}

(SEC)

(LB-SEC)

/

TUBE 23: (27"/i 72.8 0.0319 0.3897 ROW 114: (118 ! )

184.6 0.0296 0.9189 140:. (144 11 )

213.3 0.0294 1.0527 NUMBER OF 6742 184.6 0.0296 0.9189 iJ TUBES 7380 173.7 0.0301

0. 8791 BREAK OPENING 0.01 184.6 0.0296 0.9189 TIME (SEC) 0.005 187.0 0.0309 0.9697
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