ML18227B015

Submit Revised ECCS Calculations Supplemental Information Performed Using Rated Power Level of 2200 Mwt to Improve Clarity

ML18227B015
Person / Time
Site:	Turkey Point
Issue date:	01/03/1977
From:	Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-77-1
Download: ML18227B015 (40)

Text

NRC FORM 195 US, NUOLSAR RSOULATORSQMMISS ION DOCKET NUMB g-NI ~ 50-250 25 FILE NUMBER NRC DISTRIBUTION FDR PART 50 DOCKET MATERIAL TP: V. STELLO, JR. FROM: FLORDIA POWER & LIGHT CO ~ DATE OF DOCUMENT MIAMI, FLORDIA 1/3/77 R.E. UHRIG DATE RECEIVED r

1/10/77 DLETTER ,

ClNOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED JHIORIGINAL "la UNC LASS IF I E D lI 0COPV, I II I 'S VT S I

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40 DESCRIPTION ENCLOSURE, PE. THEIR,12/30/76..SUBMITTAL,

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... RESULTSrOFMHE.REVISED ECCS CALCULATXONS ......

SUPPL~~AL INFORMATION,..

( 40 CYS. RECEIVED).

( 20 PAGES)

ACKNOVKEDGED PLANT ~:

TURKEY PT. f/ 3 a 4

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. SAFETY FOR ACT ION/INFO RM ATI ON SAB 1 11 77 ASSIGNED AD:

N O- l A I Nl A A APIS

. MOJEC MANA ER S

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MIPC ERNST CASE K:JIGHT BALLARD HANAUER SIHWEIL 'PERATXNG REACTORS SPANGLER IARLESS PAWLICK STELLO SITE TECH

'.'ROJECT MANAGEMENT REA'CTOR'AFE OPERATINC TECH" GAMMIIIL-"yAq "K>""">'T BOYD ROSS EISENHUT STEPP P, COLLIiVS NOVAK HULMAN =

. HOIJSTQiV. ROSZTOCZY PETERSON CIIECK BUTLE SITE ANALYSIS MELTZ VOLLlER HELTEMES AT& I BUNCH SKOVHOLT SALTZMAN J COLLINS RUTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER I LPDR NAT LAB B 00 TIC:

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FLORIDA POWER & LIGHT COMPANY

~ 1iyfoh Doc1 ~i Cloi'k January 3', 197 7 L-77-1 0 ffice of Nuclear Reactor Regulation Attn: Victor Stello, Jr , Director Division of Operating Reactors U. S. Nuclear Regulatory 'Commission p g, ygggAa KCIIIIT0l5 Washington, D. C. 20555

Dear Mr. Stello:

Re". Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 ECCS Reevaluation Su lemental information On December 30, 1976, (L-76-438), Florida Power & Light Company forwarded the resul+s of the revised ECCS calcu-lations performed using a rated power level of 2200 Migt.

Several of the pages in our December 30, 1976, trans-mittal have been revised to improve their clarity. A copy of the revised reoort is forwarded herewith.

Very truly yours,

~~DEÃ Robert E. Uhrig Vice Presiden+

REU/GDW/hlc Attachm nt cc; Norman C. Moseley, Region 1X Robert Lowenstein, Esp.

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TABLE LARGE BREAK TIME SE UENCE OP EVENTS STEAM GENERATOR 10% TUBE PLUGGING DECL (CD 0.4)

(Sec)

START 0.0 Reactor Trip Signal 0:595 S. I. Signal 0.67 Acc. Zng ection 16. 3 End of Bypass 27.52 End of Blowdown 27.66 Bottom of Core Recovery 46. 59 Acc. Empty 61. 02 Pump Injection 25.67

II TABLE 2 LARGE BREAK STEAM GENERATOR 10% TUBE. PLUGGING DECL

'(CD~0. 4)

Results Peak Clad Temp. '.F 2190 Peak Clad Location Ft. 6.0.

Local Zr/H20 Rxn(max)% lle922 Local Zr/H20 Location Ft. 6.0 Total Zr/H20 Reaction <0. 3 Hot Rod Burst Time sec 22. 8 Hot Rod Burst Location Ft. 6.0

'et Calculation Core Power Mwt 102% of 2200 Peak Linear Power kw/ft 102% of 12. 61 Peaking Factor 2.22 Accumulator Water Volume (ft 3

) 87S (per accumulator)

Fuel region + cycle analyzed Cycl.e ~Re 1ou UNITS 3 and 4

C TABLE 3 /

LARGE BREAK VOLE'.55 CONTAINiKNT DATA (DRY CONTAItPiiENT)

NET FREE x 10 Ft INITIAL CONDITIONS Pressure 14 7 psia Temperature 90 'F RWST Temperature 39 'F k

Service Water Temperature 63 'F Outside Temperature 39 'F SPRAY SYSTEM Number of Pumps Operating Runout Plow Rate r.

1450 gpm Actuation Time 26 secs SAWeGUARDS FAN COOLERS Number of Fan Coolers Operating Minimum Post Accident Initiation Time for Fan Coolers 26 secs

ill C l U

ri

TABLE 3 (Continued)

LARGE BREAK CONTALWiENT DATA (DRY CONTAVa~1ENT)

STRUCTURAL HEAT SINKS Thickness (In) Area (Ft )

Steel 0. 03 31,400 Steel 0. 063 107, 158 Steel 0.1 56,371 Steel 0.2 57,185 Steel 0. 24 9,931 Steel 0. 2898 Concrete 24. 0 136,000 Steel 0. 4896 23,677 Steel 0,6396 6,537 Steel 0.8904 4,915 Steel 1.256 27,802 Steel 1.56 5,307 Steel 2.0 668 Steel 2.75 1268. 7 Steel 5.5 1277.4 Steel 9.0 260.4 Stainless 0.14 Concrete 24.0 14,392 Stainless 0.44 768 Stainless 2. 126 3s 704 Stainless 0.007 102,400 Concrete 24. 0 59,132

t TABLE REFLOOD MASS AND ENERGY RELEASES 'FOR LIMITING CASE DECLG (C =0.4) AND 10% STEAM GENERATOR TUBE PLUGGING TIME TOTAL MASS FLOWRATE TOTAL EPRGY FLOUR'ATE (SEC). (LBM/SEC) 10 BTU/SEC) 46.589 0.0 0.0 48.714 0. 0415 "0.0005 54.286 35.50 0.4614 64.436 95.65 1. 189

?7.136 98. 17 1. 219 92.136 103. 9 1. 280 107.936 220.9 1.603 124.236 . 263.2 1.678 159.236 274. 8 1.607 19 7. 536 281. 5 1.514

l 1

TABLE 5 BROKEN LOOP. ACCUMULATOR FLOP TO CONTAINMENT FOR LIMITING C&E DECLG (C =0.4) 10X D.

STEAM GENERATOR TUBE PLUGGING TIME SEC) MASS FLOmmTZ (LBM/SEC) 0.0 0.0

0. 02 2723.5 2.00 2276. 0 4.00 1994. 9 6.00 1793. 1

8. 00 1645. 5

>0. 0 1526. 4

15. 0 1302. 5

20. 0 1137. 8

25. 0 1034. 6

30. 0 954. 2

35. 0 887. 0

38. 9 842. 6

I0,833-I l.05 I. 00 0.95

0. 90 CD 0.85 0.80 0.75 IO 2 II 6 8 IOI 2 0 6 8 IO 2 6 8IO TIME (SECONDS)

Figure 1 Fluid Quality - DECLG (CD = 0.4)

l0,833-2 30 20 UJ cv IP o- 0 I

CD CD 6.O Ft;

- IO

-20

-30 IOO 2 0 6 8 10 2. iI 6 8 IO 2 . 0 6 8 l03 TIME (SECONDS)

Figure 2 Mass Velocity - DECLG (CD = 0.4)

l I 1J tt li

pl IO, 833-3 io" 8

6' 2

) I l08 2

l02 8

6 I

I l0 6

~ 6.0 Ft-l00 0 l00 200 '00 TIME (SECOHDS)

Figure 3 Heat Transfer Coefficient - DECLG (CD = 0.4)

t 2500 2000 l500 l000 500

.0 0'0 T I thE (SECONDS) 20 30 Figure 4 Core Pressure - DECLG (Cp = 0.4)

l0,833-5 llxlO" exlo'xio~

Sxlo U

g 3x IO~

lxlo"

-lxlo' 10 20 30 TIME (SECONDS)

Figure 5 Break Flow Rate- DECLG tCD =0.4)

75 50 25 0

-25

-50

-75 IO 20 30 TlME (SECONDS)

Figure 6 Core Pressure Drop - DECLG (CD = OA)

l0,833-7 2500 2000 Cl CD I

CD 6.O.Ft; l 500 l000 h W

500 0

0 l00 TIME (SECONDS) 300'igure 7 Peak Clad Temperature - DECLG (C = 0.4)

D

l0,833-8 2000 l750

!500 I 250 l000 I

a 750 500 6.0 Ft.

250 0

0 IOO 200 300 TIME (SECONDS)

Figure 8 Fluid Temperature - DECLG {CD = 0.4)

10,833-9 lOOQO 7500 5000 2500 l(e C)

-2500

-5000

-7500

-I0000 0 l0 20 30 TIME (SECOHDS)

Figure 9 Core Flow - Top and Bottom - DECLG (CD = 0.4)

2.00 I.75 I. 50 I. 25 I- l.pp o 0,75

0. 50

0. 25

0. 00 0 25 50 75 lpp 125 l50 l75 200

/

TIME (SECOHDSj CI CO CD Figure 10 Ref lood Transient - DECLG (CD = 0.4) CD I

Core Inlet Velocity Ct

20.0

'7.5 DOWHCOt4ER LEVEL

15. 0

12. 5

10. 0 7.5 5.0 CORE LEVEL 2.5 0.0 0 25 50 75 100 125 150 175 200 TIME (SECONDS)

Figure ll Ref lood Transient - OECLG (CO = 0.4)

Downcomer and Core Water Levels

l0,833-I2

'000 5000

%000 3000 2000 CD IOOO 0

0 IO 20 30 TIME (SECONDS)

Figure 12 Accumulator Flow (Blowdown) - DECLG (C> = 0.4)

8.0 6.0 I

II. 0 I t

I 2.0 I

t 0.0 0 QO 80 I20 I60 200 TIME (SECONDS)

Figure 13 Pumped ECCS Flow (Ref lood) - DECLG (CD = 0.4)

30.

25 20 l5 I

l0 I-ED 0

0 %0 80 120 !60 200 200 280 320 360 %00 TIME (SECONDS)

Figure 14 'ontainment Pressure -.DECLG (C~ 0.4)

0 l.o 0.8 0.6 IA o 0. ll 0.2 0.0 0 l0 20 30 TlME (SECONDS)

Figure 15 Core Power Transient - DECLG (CD = 0.4)

55x I 06

%5x IO 35xl06 25x I 06 l5xl06 5xl06

-.5x IO6 0 IO 20 30 TIME (SECONDS)

Figure 16 Break Energy Released to Containment

l0,833- l7 I I 00 U

O I 000 I

I U

1 900 l-CCl I

800 UJ CD U

U UJ CD 700 CD UJ 600 I

I-UJ 500

'I CQ UJ %0 C5 CD CD 300 I

UJ 200 l

ID IOO 0

0 IOO 200 300 TIME (SECOIIDS)

Figure 17 Containment Wall Condensing Heat Transfer Coefficient

(0,833- l7 I IOO U

O I 000 I

I U

I CC 900 I

le I

800 UJ CD U

U UJ ED 700 CD UJ U

C/)

600 CC I

I-UJ 500 C9 Cll UJ KO Ch ED 300 I

UJ 200 I

C)

CD IOO 0

0 IOO 200 300 TIME,.(SECONDS)

Figure 17 Containment Wall Condensing Heat Transfer Coefficient

0 p Q

0 l 0, 833- l7 I l00 U

O 000 I

I-U I

900 I

Cl I

800 M

CD LL U

LU 700 600 500 CO Ul %00 C5 CD 300 I

UJ 200 I

l00 0

0 l00 200 300 TIME (SECONDS)

Figure 17 Containment Wall Condensing Heat Transfer Coefficient

e i'