ML20195C627
| ML20195C627 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/28/1999 |
| From: | BWR OWNERS GROUP |
| To: | |
| Shared Package | |
| ML20195C588 | List: |
| References | |
| BAW-2346P-ADD, BAW-2346P-ADD-R, BAW-2346P-ADD-R00, NUDOCS 9906080237 | |
| Download: ML20195C627 (15) | |
Text
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1 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 ADDENDUM TO TOPICAL REPORT BAW-234P (Non-Proprietary)
CR-3 PLANT SPECIFIC MSLB LEAK RATES 9906000237 990528"%
PDR ADOCK 05000302 P pm,
e U.S. Nuclear Regulatory Commission Addendum A
' 3F0599-21 Page 1 of 14 ADDsNDUM A- CR-3 PLANT SPECIFIC MAIN STEAM LINE BREAK LEAK RATES:
This addendum provides plant specific accident condition leak rates for the CR 3. The leak rates are intended to replace the generic bounding accident leak rates. These ,
plant specific leak rates are based on the thermal and structural response of the steam generators associated with the plant specific Main Steam Line Break (MSLB) thermal hydraulic analysis results. Although the results of this addendum are based on leak testing and methodology developed as part of a Babcox and Wilcox Owners Group (B&WOG) proprietary program, the actual results of this addendum are specific to CR-3 and therefore are not considered B&WOG proprietary.
l A.1 METHOD OF ANALYSIS:
The method of analysis used for determining plant specific leak rates is identical to that outlined in Topical Report BAW-2346P and implemented in the body of this document. !
The tube-to-tubesheet bore A dilations for the CR-3 plant specific MSLB transient are !
used with the results from the mockup leak tests to determine the leak rates as a j function of tubesheet radius.
i The CR-3 plant specific A dilations as a function of tubesheet radius are summarized in Table A-1 ior the intact steam generator and in Table A-2 for the faulted steam generator. The tables include the bounding dilations for the time of maximum AP from limiting 25% plugged tube case.
U.S. Nuclear Regulatory Commission Addendum A j 3F0599-21 l Page 2 of 14 I
TABLE A-1 CR-3 MSLB A DILATION versus TUBESHEET RADIUS (intact steam generator, plugged tube case)
T/S A DILATION (mils) TUBE RADIUS UPPER T/S LOWER T/S LOAD (in) RAD CIRC RAD CIRC (Ibs) 3 -0.73 -0.67 -0.88 -0.75 424 4 -0.84 -0.71 -0.98 -0.82 424 5 -0.85 -0.74 -0.96 -0.85 425 )
6 -0.85 -0.76 -0.95 -0.87 426 7 -0.85 -0.77 -0.95 -0.88 428 8 -0.85 -0.78 -0.94 -0.89 431 9 -0.84 -0.79 -0.94 -0.89 434 l 10 -0.83 -0.79 -0.93 -0.90 438 !
11 -0.82 -0.80 -0.92 -0.90 442 4 12 -0.81 -0.80 -0.91 -0.90 447 13 -0.80 -0.80 -0.90 -0.90 453 14 -0.79 -0.80 -0.89 -0.90 459 15 -0.77 -0.80 -0.88 -0.90 466 16 -0.76 -0.79 -0.86 -0.90 473 17 -0.75 -0.79 -0.85 -0.90 481 18 -0.73 -0.79 -0.84 -0.89 489 19 -0.72 -0.79 -0.83 -0.89 497 20 -0.70 -0.78 -0.81 -0.89 506 21 -0.69 -0.78 -0.80 -0.88 515 22 -0.67 -0.77 -0.78 -0.88 525 23 -0.66 -0.77 -0.77 -0.87 535 24 -0.64 -0.76 -0.75 -0.87 546 25 -0.63 -0.76 -0.73 -0.86 557 26 -0.61 -0.75 -0.72 -0.86 568 27 -0.59 -0.75 -0.70 -0.85 580 28 -0.57 -0.74 -0.68 -0.85 592 29 -0.55 -0.74 -0.66 -0.84 604 30 -0.54 -0.73 -0.64 -0.83 616 _
31 -0.52 -0.72 -0.62 -0.83 629 32 -0.50 -0.72 -0.60 -0.82 642
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l'.S. Nuclear Regulatory Commission Addendum A 3F0599-21 Page 3 of 14 TABLE A-1 CR-3 MSLB A DILATION versus TUBESHEET RADIUS (intact steam generator, plugged tube case)
T/S A DILATION (mils) TUBE RADIUS UPPER T/S LOWER T/S LOAD (in) RAD CIRC RAD CIRC (Ibs) 33 -0.48 -0.71 -0.58 -0.81 656 34 -0.46 -0.70 -0.56 -0.81 669 35 -0.44 -0.70 -0.54 -0.80 683 36 -0.42 -0.69 -0.52 -0.79 697 37 -0.41 -0.68 -0.50 -0.79 711 38 -0.39 -0.67 -0.48 -0.78 726 39 -0.37 -0.67 -0.46 -0.77 740 40 -0.36 -0.66 -0.44 -0.76 755 41 -0.34 -0.65 -0.42 -0.75 770 42 -0.33 -0.64 -0.40 -0.75 785 43 -0.31 -0.64 -0.38 -0.74 800 44 -0.30 -0.63 -0.36 -0.73 816 45 -0.29 -0.62 -0.34 -0.72 831 46 -0.28 -0.61 -0.32 -0.71 847 47 -0.27 -0.61 -0.30 -0.70 863 48 -0.27 -0.60 -0.28 -0.69 880 49 -0.26 -0.59 -0.25 -0.69 897 50 -0.24 -0.59 -0.23 -0.68 915 51 -0.23 -0.58 -0.20 -0.67 934 52 -0.20 -0.57 -0.16 -0.66 953 53 -0.17 -0.56 -0.12 -0.65 97,4 54 -0.10 -0.56 -0.05 -0.64 996 55 0.01 -0.55 0.06 -0.63 1021 66 0.28 -0.54 0.30 -0.61 1050 57 0.80 -0.52 0.74 -0.59 1083 57.72 0.75 -0.52 0.64 -0.58 1083 I
c:
U.S. Nuclear Regulatory Commission Addendum A 3F0599-21 Page 4 of 14 TABLE A-2 CR-3 MSLB A DILATION versus TUBESHEET RADIUS (faulted steam generator, plugged tube case)
T/S A DILATION (mils) TUBE RADIUS UPPER T/S LOWER T/S LOAD (in) RAD CIRC RAD CIRC (Ibs) 3 -0.89 -0.75 -1.02 -0.83 -159 4 -1.01 -0.82 -1.14 -0.91 -159 5 -0.99 -0.86 -1.09 -0.95 -157 6 -0.99 -0.88 -1.08 -0.98 -155 7 -0.99 -0.90 -1.08 -0.99 -152 8 -0.99 -0.91 -1.07 -1.00 -149 9 -0.98 -0.92 -1.07 -1.01 -144 10 -0.97 -0.92 -1.06 -1.02 -139 11 -0.96 -0.93 -1.05 -1.02 -134 )
12 -0.94 -0.93 -1.03 -1.02 -127 13 -0.93 -0.93 -1.02 -1.02 -120 14 -0.92 -0.93 -1.01 -1.02 -112 15 -0.90 -0.93 -0.99 -1.02 -104 16 -0.89 -0.92 -0.98 -1.02 -95 17 -0.87 -0.92 -0.96 -1.02 -85 18 -0.85 -0.92 -0.95 -1.01 -75 19 -0.84 -0.92 -0.93 -1.01 -65 20 -0.82 -0.91 -0.92 -1.00 -53 i 21 -0.80 -0.91 -0.90 -1.00 -42 !
22 -0.78 -0.90 -0.88 -0.99 -29 23 -0.76 -0.90 -0.86 -0.99 -17 24 -0.74 -0.89 -0.84 -0.98 -3 25 -0.72 -0.88 -0.82 -0.98 10 ;
26 -0.70 -0.88 -0.80 -0.97 25 27 -0.68 -0.87 -0.78 -0.96 39 28 -0.66 -0.86 -0.76 -0.96 54 29 -0.64 -0.86 -0.73 -0.95 70 30 -0.62 -0.85 -0.71 -0.94 85 31 -0.59 -0.84 -0.69 -0.93 101 32 -0.57 -0.83 -0.66 -0.93 118 1
F
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U.S. Nuclear Regulatory Commission Addendum A 3F0599-21 Page 5 of 14 TABLE A-2 CR-3 MSLB A DILATION versus TUBESHEET RADIUS (faulted steam generator, plugged tube case)
T/S A DILATION (mils) TUBE RADIUS UPPER T/S LOWER T/S LOAD (in) RAD CIRC RAD CIRC (Ibs) 33- -0.54 -0.82 -0.64 -0.92 135 34 -0.52 -0.82 -0.61 -0.91 152 35 -0.50 -0.81 -0.59 -0.90 169 36 -0.47 -0.80 -0.56 -0.89 187 37 -0.45 -0.79 -0.53 -0.88 205 38 -0.43 -0.78 -0.51 -0.87 223 39 -0.40 -0.77 -0.48 -0.86 242 40 -0.38 -0.76 -0.45 -0.85 260 41 -0.36 -0.75 -0.43 -0.84 279 42 -0.34 -0.74 -0.40 -0.83 298 43 -0.32 -0.73 -0.38 -0.82 318 44 -0.30 -0.72 -0.35 -0.81 337 45 -0.28 -0.71 -0.32 -0.80 357 46 -0.26 -0.70 -0.30 -0.79 377 47 -0.25 -0.69 -0.27 -0.78 398 l 48 -0.23 -0.68 -0.24 -0.77 419 49 -0.21 -0.67 -0.21 -0.76 440 50 -0.19 -0.66 -0.18 -0.75 462 51 -0.16 -0.66 -0.14 -0.74 485 52 -0.12 -0.65 -0.10 -0.72 509 53 -0.07 -0.64 -0.04 -0.71 534 54 0.01 -0.62 0.04 -0.70 561 !
55 0.14 -0.61 0.17 -0.68 591 l 56 0.44 -0.60 0.44 -0.67 624 l 57 1.01 -0.58 0.93 -0.65 663 I
57.72 0.92 -0.57 0.81 -0.63 663 l
II .
U.S. Nuclear Regulatory Commission Addendum A 3F0599-21 Page 6 of 14 A.2 ' CR-3 MSLB LEAK RATE VS. TUBESHEET RADIUS:
The A dilation versus tubesheet radius values from Tables A and A-2 are to determine the CR-3 plant specific MSLB accident leak rate versus tubesheet radius.
The A dilation that resulted in the least amount of contact pressure was used to determine the leak rates as a function of tubesheet radius. The smallest contact pressure, and therefore largest leakage, occurs at the largest positive a dilation. For the cases where both . the circumferential and radial dilations are negative l (compressive), the least negative A dilation was used. The limiting dilations from Table A-1 and Table A-2 were used to select the appropriate leak rate.
1 A summary of the limiting A dilations and resulting accident leak rates for the intact steam generator is contained in Table A-3 and also in Figures A-1 and A-2. A j condensed numerical summary of the leak rates is provided in Table A-4.
A summary of the limiting a dilations and resulting accident leak rates for the faulted steam generator is contained in Table A-5 and also in Figures A-3 and A-4. A condensed numerical summary of the leak rates is provided in Table A-6.
. l U.S. Nuclear Regulatory Commission Addendum A 3F0599-21 Page 7 of 14 I
I TABLE A-3 CR-3 MSLB LEAK RATE versus TUBESHEET RADIUS (intact steam generator, plugged tube case) tubesheet upper tubesheet lower tubesheet radius limiting A leak rate limiting A leak rate dilation dilation (in) (mils) (gpm) (mils) (gpm) 3 -0.67 7.10E-05 -0.75 7.10E-05 4 -0.71 7.10E-03 -0.82 7.10E-05 5 -0.74 7.10E-05 -0.85 7.10E-05 6 -0.76 7.10E-05 -0.87 7.10E-05 7 -0.77 7.10E-05 -0.88 7.10E-05 ,
8 -0.78 7.10E-05 -0.89 7.10E-05 I 9 -0.79 7.10E-05 -0.89 7.10E-05 10 -0.79 7.10E-05 -0.90 7.10E-05 11 -0.80 7.10E-05 -0.90 7.10E-05 12 -0.80 7.10E-05 -0.90 7.10E-05 13 -0.80 7.10E-05 -0.90 7.10E-05 14 -0.79 7.10E-05 -0.89 7.10E-05 15 -0.77 7.10E-05 -0.88 7.10E-05 16 -0.76 7.10E-05 -0.86 7.10E-05 '
17 -0.75 7.10E-05 -0.85 7.10E-05 18 -0.73 7.10E-05 -0.84 7.10E-05 19 -0.72 7.10E-05 -0.83 7.10E-05 20 -0.70 7.10E-05 -0.81 7.10E-05 21 -0.69 7.10E-05 -0.80 7.10E-05 22 -0.67 7.10E-05 -0.78 7.10E-05 23 -0.66 7.10E-05 -0.77 7.10E-05 24 -0.64 7.10E-05 -0.75 7.10E-05 25 -0.63 7.10E-05 -0.73 7.10E-05 26 -0.61 7.10E-05 -0.72 7.10E-05 27 -0.59 7.10E-05 -0.70 7.10E-05 28 -0.57 7.10E-05 -0.68 7.10E-05 29 -0.55 7.10E-05 -0.66 7.10E-05 30 -0.54 7.10E-05 -0.64 7.10E-05 31 -0.52 7.10E-05 -0.62 7.10E-05 32 -0.50 7.10E-05 -0.60 7.10E-05
~. .
U.S. Nuclear Regulatory Commission Addendum A 3F0599-21 Page 8 of 14 TABLE A-3 CR-3 MSLB LEAK RATE versus TUBESHEET RADIUS (intact steam generator, plugged tube case) tubesheet upper tubesheet lower tubesheet radius limiting A leak rate limiting A leak rate dilation dilation (in) (mils) (gpm) (mils) (gpm) 33 -0.48 7.10E-05 -0.58 7.10E-05 34 -0.46 7.10E-05 -0.56 7.10E-05 35 -0.44 7.10E-05 -0.54 7.10E-05 36 -0.42 7.10E-05 -0.52 7.10E-05 37 -0.41 7.10E-05 -0.50 7.10E-05 38 -0.39 1.90E-04 -0.48 7.10E-05 39 -0.37 1.90E-04 -0.46 7.10E-05 40 -0.36 1.90E-04 -0.44 7.10E-05 41 -0.34 1.90E-04 -0.42 7.10E-05 42 -0.33 1.90E-04 -0.40 1.90E-04 43 -0.31 1.90E-04 -0.38 1.90E-04 44 -0.30 1.90E-04 -0.36 1.90E-04 45 -0.29 1.90E-04 -0.34 1.90E-04 j 46 -0.28 1.90E-04 -0.32 1.90E-04 47 -0.27 1.90E-04 -0.30 1.90E-04 48 -0.27 1.90E-04 -0.28 1.90E-04 49 -0.26 1.90E-04 -0.25 1.90E-04 50 -0.24 1.90E-04 -0.23 1.90E-04 51 -0.23 1.90E-04 -0.20 1.90E-04 52 -0.20 1.90E-04 -0.16 3.83E-04 53 -0.17 3.83E-04 -0.12 3.83E-04 54 -0.10 3.83E-04 -0.05 3.83E-04 55 0.01 5.41 E-04 0.06 5.41 E-04 56 0.28 8.23E-04 0.30 8.23E-04 57 0.80 5.72E-03 0.74 5.72E-03 57.72 0.75 5.72E-03 0.64 1.37E-03 l
l l
l
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U.S. Nuclear Regulatory Commission Addendum A 3F0599-21 Page 9 of 14 FIGURE A-1 CR-3 MSLB LEAK RATES FOR UPPER TUBESHEET (intact steam generator)
Leak Rate per Indication versus Tubesheet Radius (CR-3 MSLB accident, with 25% plugged tubes) 1.E+00 !,,,, i , , , , , , , , , , , ,,,, , , , ,
, j t , , , , , , , , , , 1 . , ,,,, ,,,,
1.E 01 -g -i l -i + ' ' -
" - i-
^
E El l l l l:
see Table A-4 for numerical values ll l l l l c., , , , , , , , , , , , , , , , , ,,,, , , ,,
5 1.E 02 - i t, i, t t,- t, t,-i, t, t, t, t, ', - t, l t, i, d, i,--i, t -i, -i. n E ,
x , , ,
1.E [., - - e, e,r,-
-,4 u , , , , , ,
- a. .: i, , , ,
, , , i i , i i i i i ,
,iii
,i a ., , , , , , , , , , , , , , , , ,,
l.E g,..,'-~'.' -'---'
l '- -i-+ ++ - 4+ ,
,,,, , , I,-
, ,. ., , ,. t ,, ,,,, , ,,
, , , , , , , , , , , , , , ,, ,,,, ,l , ,,
1.E 05 ,
0 10 20 30 40 50 60 l
Tubesheet Radius (inch)
I' FIGURE A-2 CR-3 MSLB LEAK RATES FOR LOWER TUBESHEET (intact steam generator)
Leak Rate per Indication versus Tubesheet Radius (CR 3 MSLB accident, with 25% plugged tubes) 1.E+00 , , , , , , , , , ,,,, , , , , ,,,, , , , ,
- , , , , , , , , 1 I , , , , , , ,,,, f , , ,
"l , , , , , , , , , , , , , , , ,,,, , , , ,
, 1.E-01 -I",',",",- ",",",",- , ,- ', ', ~", " ', ,
E a, : l l l l 'l see Table A 4 for numerical values 'l l l l l 5 1.E i , r,-'
, , -i,- i,-,,,, , , , ,
, , , , ,,,F,
,, - ,-l-H g , , , , ,
1.E !- ~, ~, ,
, ,,~,+ , , , , ~ , - ~ , , ' ,, ,, - , , , - , - ~, ~ , ,-
u.
a 1.E , , , , , , , ,
i;, ", , ",
- ", ', ' * * '", * ~' -", ~
I n, t -t, - t, i, - t, t,
- , , , , t , , , , , , , , , , t ,,,, l , ,,
l.E-05 0 10 20 30 40 50 60 Tulesheet Radius (inch)
U.S. Nuclear Regulatory Commission Addendum A 3F0599-21 Page 10 of 14 TABLE A-4 ,
SUMMARY
of 95/50 LEAK RATE vs. TUBESHEET RADIUS I (intact steam generator, plugged tube case) l CR-3 MSLB Accident Condition Upper Tubesheet Lower Tubesheet l Radius Leak Rate Radius Leak Rate (inch) (gpm) (inch) (gpm) ,
> 3, s 37 7.10E-5 > 3, s 41 7.10E-5
> 37, s 52 1.90E-4 > 41, s 51 1.90E 4
> 52, s 54 3.83E-4 > 51,5 54 3.83E-4
> 54, s 55 5.41 E-4 > 54, s 55 5.41 E-4
> 55, s 56 8.23E-4 > 55, s 56 8.23E-4
> 56 5.72E-3 > 56 5.72E-3 Radius = location of tube center relative to the center of )
I i
i
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U.S. Nuclear Regulatory Commission Addendum A 3F0599-21 Page 11 of 14 TABLE A-5 CR-3 MSLB LEAK RATE versus TUBESHEET RADIUS (faulted steam generator, plugged tube case) tubesheet upper tubesheet lower tubesheet radius limiting A leak rate limiting A leak rate dilation dilation (in) (mils) (gpm) (mils) (gpm) 3 -0.75 7.10E-05 -0.83 7.10E-05 4 -0.82 7.10E-05 -0.91 7.10E-05 5 -0.86 7.10E-05 -0.95 7.10E-05 6 -0.88 7.10E-05 -0.98 7.10E-05 7 -0.90 7.10E-05 -0.99 7.10E-05 8 -0.91 7.10E-05 -1.00 7.10E-05 9 -0.92 7.10E-05 -1.01 7.10E-05 10 -0.92 7.10E-05 -1.02 7.10E-05 11 -0.93 7.10E-05 -1.02 7.10E-05 12 -0.93 7.10E-05 -1.02 7.10E-05 13 -0.93 7.10E-05 -1.02 7.10E-05 14 -0.92 7.10E-05 -1.01 7.10E-05 15 -0.90 7.10E-05 -0.99 7.10E-05 16 -0.89 7.10E-05 -0.98 7.10E-05 17 -0.87 7.10E-05 -0.96 7.10E-05 18 -0.85 7.10E-05 -0.95 7.10E-05 19 -0.84 7.10E-05 -0.93 7.10E-05 20 -0.82 7.10E-05 -0.92 7.10E-05 j 21 -0.80 7.10E-05 -0.90 7.10E-05 22 -0.78 7.10E-05 -0.88 7.10E-05 23 -0.76 7.10E-05 -0.86 7.10E-05 24 -0.74 7.10E-05 -0.84 7.10E-05 25 -0.72 7.10E-05 -0.82 7.10E-05 26 -0.70 7.10E-05 -0.80 7.10E-05 '
27 -0.68 7.10E-05 -0.78 7.10E-05 28 -0.66 7.10E-05 -0.76 7.10E-05 ;
29 -0.64 7.10E-05 -0.73 7.10E-05 30 -0.62 7.10E-05 -0.71 7.10E-05 31 -0.59 7.10E-05 -0.69 7.10E-05 32 -0.57 7.10E-05 -0.66 7.10E-05 I
i a
U.S. Nuclear Regulatory Commission Addendum A 3F0599-21 Page 12 of 14 TABLE A-5 CR-3 MSLB LEAK RATE versus TUBESHEET RADIUS (faulted steam generator, plugged tube case) tubesheet "u~pper tubesheet lower tubesheet radius limiting A leak rate limiting A leak rate dilation dilation (in) (mils) (gpm) (mils) (gpm)
{
33 -0.54 7.10E-05 -0.64 7.10E-05 34 -0.52 7.10E-05 -0.61 7.10E-05 35 -0.50 7.10E-05 -0.59 7.10E-05 ;
36 -0.47 7.10E-05 -0.56 7.10E-05 ]
37 -0.45 7.10E-05 -0.53 7.10E-05 38 -0.43 7.10E-05 -0.51 7.10E-05 3 39 -0.40 7.10E-05 -0.48 7.10E-05 )
40 -0.38 1.90E-04 -0.45 7.10E-05 i 41 -0.36 1.90E-04 -0.43 7.10E-05 l 42 -0.34 1.90E-04 -0.40 7.10E-05 43 -0.32 1.90E-04 -0.38 1.90E-04 44 -0.30 1.90E-04 -0.35 1.90E-04 45 -0.28 1.90E-04 -0.32 1.90E-04 46 -0.26 1.90E-04 -0.30 1.90E-04 47 -0.25 1.90E-04 -0.27 1.90E 04 48 -0.23 1.90E-04 , -0.24 1.90E-04 49 -0.21 1.90E-04 -0.21 1.90E-04 50 -0.19 3.83E-04 -0.18 3.83E-04 l 51 -0.16 3.83E-04 -0.14 3.83E-04 l 52 -0.12 3.83E-04 -0.10 3.83E-04 i 53 -0.07 3.83E-04 -0.04 3.83E-04 54 0.01 5.41 E-04 0.04 5.41 E-04 55 0.14 5.41 E-04 0.17 5.41 E-04 56 0.44 1.37E-03 0.44 1.37E-03 57 1.01 5.72E-03 0.93 5.72E-03 ;
57.72 0.92 5.72E-03 0.81 5.72E-03 l
- a. .
U.S. Nuclear Regulatory Commission Addendum A
= 3F0599-21 Page 13 of 14 FIGURE A-3 CR-3 MSLB LEAK RATES FOR UPPER TUBESHEET OF FAULTED SG Leak Rate per Indication versus Tubesheet Radius (CR-3 MSLB accident, with 25% plugged tubes) 1.E+00 , , , , , , , , , ,,,, , ,,, , , , , ,,,,
, , , , , , , , ,,,, 4 ,,, , , , , l , , ,
",,,, , , 4 , ,,,, , , , 4 , f , , , , , ,
- ,,,, , , , , ,,,, , i,, , , , , , n , ,
e d. J .. l- J... J l . 1. . . i ... l - .1 ~. . .! . ! . 3 .. J . - J- d. ,... 1. 1.. J ...& .
- r , , , , , , , , ,,,, , , , , , . , , , , , ,
, ,,, t , i , , ., , ,
g,, ,I i , , ,
see Table A 6 0)r numericol values , , i i ,
5 1.E 02 - r ?, M, , ?,- M, , , ,. , , , ,- , ,. , , , , , 4, -? d,-M ,
=
, , , , t , i , ,,,, , , 4
- 1.E i , ", *, 2, 2 -
~ , ' , ,^, '
-2,'~',',-,
,l
> " " ' -
- 3, I
Q
- : i , , i i i , i i i i . , , ,
a : , i, i, ,i , , , i, i, , , , ., , ,i , , , i, , , ,
e ,,,, , , , , , , , , , . , , ,I , , , ,
a 1.E 04 - r ,, ~, ,
- 4
- ~ - -
- - - 4, ,
a a a a a e a a a a e a a e e a a e a a i e a e .
0 10 20 30 40 50 60 Tubesheet Radius (in)
FIGURE A-4 CR-3 MSLB LEAK RATES FOR LOWER TUBESHEET OF FAULTED SG Leak Rate perIndication versus Tubesheet Radius (CR-3 MSLB accident, with 25% plugged tubes) 1.E+00 ,
= , ,,, , , , , , , , , , , , , , , , , , , ,
= , , , , , , , , , , , ., , , , , , t , , ,
" , 4 t
" ,, ,,, , , , , , i , , , , , , , , , ! , , , , , ,
, . , , , , , , , t , , , i , , , , ! , ,
1.E 01 - r: t, ri -i, - t i,t ;- - 1, i,-i, t,- l,,,-i i - t, - 1 t t -i, l-i, H, , -
, , , , , , , l . , ,
g - , , , , , ,
sec Table A 6 fbr numerical values e
,e i ,
, , ,i 8 1.E 02 - r ,, r, ,, ~, - , , -
c-
, , , , ,,,, , , , , -c,r-a , , , , , , , , ,,,, , , , , , , ,
- - l i l'; --i-w a
1.E 03 - r-l
- , t, ~i, - t, -
- e , ,
i,t, i, t
, i i i t, t, t, i,-- ~i-i ' i,- 1., tli
, i , ,
i , i
. r ,J .i i e , , , ,i , , , , , , , , ,i ,i , ,. . I . , , ,
a , , , , , , , , ,,,, , , , ,
1.E 04 - .p, ~, ~, ,
-- - - - ~~ ~ ~~-
- l , ~, - r
, , > ~ , , - *, '
1.E-05 ,
O 10 20 30 40 50 60 Tubesheet Radius (in) 1 L
I
. . \
1
- U.S. Nuclear Regulatory Commission Addendum A l e 3F0599-21 Page 14 of 14
]
TABLE A 6
SUMMARY
of 95/50 LEAK RATE vs. TUBESHEET RADIUS (faulted steam generato6 plugged tube case)
CR-3 MSLB Accident Condition Upper Tubesheet Lower Tubesheet Radius Leak Rate Radius Lok Rate l (inch) (gpm) (inch) upm) i l > 3, s 39 7.10E-5 > 3, s 42 7.10E-5 I
> 39, s 49 1.90E-4 > 42, s 49 1.90E-4
> 49, s 53 3.83E-4 > 49, s 53 3.83E-4
> 53, s 55 5.41 E-4 > 53, s 55 5.41 E-4
> 55, s 56 1.37E-3 > 55, s 56 1.37E-3 l > 56 5.72E-3 > 56 5.72E-3 Radius = location of tube center relative to the center of SG I
l 1
l i
- l l
l l l
l l
l