ML20213G628

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Forwards Addl Info Supporting Profile Submitted in FSAR Amend 27 as Figure 3.11.B.1-1 Re time-dependent Temp Profile Inside Containment,Per SER Open Item 1
ML20213G628
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 11/13/1986
From: Bailey J
GEORGIA POWER CO.
To: Youngblood B
Office of Nuclear Reactor Regulation
References
GN-1178, NUDOCS 8611180236
Download: ML20213G628 (24)
v • d • e


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Georgia Pbwer Cormany ,

, Pbst Offica Box 282 '

- W ynssboro, Georgia 30830 '

Telephone 404 554-9961 404 724-8 @

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Southern Company Services, Inc.

Post Office Bo< 2625 ,

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i Birmingham, Alabama 35202' '

Teepnon. 205 8' ""

l i '0 Vogtle Project November 13, 1986 ,

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Director of Nuclear Reactor Regulation File: X7BC35 Attention: Mr. B. J. Youngblood . ,

Log: GN-1178 j j PWR Project Directorate #4 Division of PWR Licensing A i

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 C0XSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 i V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 h SER OPEN ITEM 1: EQUIPMENT QUALIFICATION 1

Dear Mr. Denton:

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\

As requested during a conference call with cyour staff on November 10, 1986, we are providing additional information concerning the Vogtle time-dependent

' temperature profile inside contaihment. The information is being provided in support of the profile which was submitted in FSAR Amendment 27 as Figure 3.11.B.1-1 (sheet 9 of 12). The supporting data is provided in the following attachments: .i

1. Attachment 1: Input Data '

4 I Attachment 2: Output Profile  ;

Attachment 3: FSAR Tables 6.2.1-2, 3, 6.2.2 Assumptions

- Attachment 4: FSAR Tables 6.2.1.4, 5 -~ Heat Sink Evaluation il Attachment 5: FSAR Tables 6.2.1-65, 68 - Sequence of Events is N We will be available to discuss the input data and assumptions with your staff '

, on November 19, 1986. Should you require additional information, please do

,not hesit' ate to call. [

i Since re'ly ,  !

  • 4L J. A. Bailey Project Licensing Manager

~

JAB /sm s Attachment 5

8611180236 861113 i

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_ . . . _ _ . _ _ - . . - _ - _ . . . _ ~ . .

Director of Nuclear Reactor Regulation File: X7BC35 November 13, 1986 Log: GN-1178 Page 2 xc: R. E. Conway R. A. Thomas-J. E. Joiner, Esquire B. W. Churchill, Esquire M. A. Miller (2)

B. Jones, Esquire G. Bockhold, Jr.

NRC Regional Administrator NRC Resident Inspector D. Feig R. W. McManus L. T. Gucwa Vogtle Project File 0870V i

A &

ATTACHMENT 1 INPUT DATA

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9 ATTACHMENT 2 OUTPUT PROFILE

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ATTACHMENT 3 ASSUMPTIONS

VEGP-FSAR-6 i

TABLE 6.2.1-2 ASSUMPTIONS FOR CONTAINMENT ANALYSIS - PART 1 CO PA T TA_

Service water temperature (*F) 95 /05 Refueling water temperature (*F) 98 QMdiY 1420 Refueling water storage tank volume (gal) 715,000 goo, coo (Not u. sed 4.c Initial Containment msta s)

Temperature (*F) 120 iga Initial pressure (psia) 15 14.7 Initial relative humidity (%) 20 50 Net free volume (ft8) 2.75 x 108 J.75 x /o '

, - - - ,--,-,-,,-,+-,,.n-.,.-..--p-.,,._ ,,w- , ,- - - , - , . - - - , - - - , , . . , _ . - . ,, ,. - _ , _ . - , . _ _ . _ , _ , _ - . , . . _ ,

VEGP-FSAR-6 TABLE 6.2.1-3 ASSUMPTIONS FOR CONTAINMENT ANALYSIS - PART 2 Accident Analysis Design Fan coolers COPAT7A Number operating 2 8 4

Flowrate per fan cooler 43,500 9 (ft / min) 8 Mdft'd'aP"f (slow speed)0 ( 7,000 full speed) 10 Heat removal capacity per fan 8.15 x 10' See ldle 2.605 x 10' cooler (Stu/h) 4 2.J-2 Spray pumps Number available 1 l 2 Flowrate per pump (gal / min) 2600 4600 3200 Amend. 10 9/84

VEGP-FSAR-6 TABLE 6.2.2-2 CONTAINMENT FAN COOLING HEAT REMOVAL CAPACITY (POST-MSLB AND LOCA MODES)

Containment Temperature (*F) Capacity (Btu /h) NSCW Temperature ('F) copA rrn

  • 10 120 6 x 10' 5.? K/4[ 95 145 13 x 10' /J K /h 95-170 21 x 10 a lX 10'6 95 195 29.5 x 10' .ff.9 t/o 95 220 38 x 10' 33.Fx /o' 95 245 46 x 10' 4 7.5 x/o
  • 95 270 55 x 10' 5 6.5 x lo ' 95 4 per er coole.r

_;.c- '

Amend. 10 9/84 4 - - - - - - - - - - - - - - - - - - - - --

D ATTACHMENT 4 HEAT SINK EVALUATION

VEGP-ESAR-6 TABLE 6.2.1-4 (SHEET 1 OF 2)

CONTAINMENT HEAT SINKS Heat Transfer Area Thickness Wall Description (ft2) Material (ft')

1. Dome 29,260.0 Epoxy 0.0008 Inorganic zinc 0.0002083 paint Carbon steel O.02083 Concrete 2.25
2. Shell 65,181.4 Inorganic zinc 0.0002083 paint Carbon steel 0.02083 Concrete 3.75
3. Miscellaneous interior 16,150.5 Epoxy 0.00154 concrete Concrete 3.0927
4. Primary shields 2106.15 Inorganic zinc 0.0002083 paint 11 Carbon steel .0.05795 Epoxy 0.001125 Concrete 1.5
5. Mechanical equipment 209.0 Stainless steel 0.0158
6. Refueling canal wall 12,909.3 Stainless steel 0.01042 Epoxy 0.00117 Concrete 2.0668
7. Miscellaneous interior 4692.7 Epoxy 0.000042 concrete Concrete 2.735
8. Miscellaneous interior 20,102.4 Epoxy 0.000042 concrete Concrete 1.806
9. Miscellaneous interior 5383.5 Epoxy 0.001125 concrete Concrete 1.67685
10. Refueling canal slab 2509.2 Stainless steel 0.02083 Concrete 4.0
11. Structural steel 198,805.0 Galvanizing 0.00033 Carbon steel 0.0218 Amend. 11 11/84

VEOP-FSAR-6 TABLE 6.2.1-4 (SHEET 2 OF 2)

Heat Transfer Area Thickness Wall Description (ft2) Material (ft2)

12. Structural steel 183,286.4 Inorganic zinc 0.000208 paint Carbon steel 0.0526
13. Piping 55,464.8 Inorganic zinc 0.000208 paint Carbon steel 0.02171
14. Piping 30,177.4 Stainless steel 0.0151
15. Piping 2666.7 Stainless steel 0.0648
16. Mechanical equipment 97,680.45 Inorganic zinc 0.000208 paint Carbon steel 0.14 11
17. Mechanical equipment 24,750.0 Inorganic zinc 0.000208 paint Carbon steel 0.0208
18. Miscellaneous steel 34,998.9 Inorganic zinc 0.000208 paint Carbon steel 0.02682
19. Basement 13,701.85 Inorganic zinc 0.000208 paint Carbon steel O.02083 Concrete 10.5
20. Reactor cavity 4262.65 Inorganic zinc 0.000208 paint Carbon steel O.02083 Concrete 8.0 Amend. 11 11/84

COPATTA CONTAIISENT HEAT SINKS HEAT TRANSFER WALL DESCRIPTION AREA (ft2 ) MATERIAL THICKNESS (ft )

1. Dame 27,720 Epoxy 0.00025 Inorganic zine paint 0.00021 Carbon steel 0.02083 Air 0.00087 Concrete 3.9
2. Shell 61,750 Inorganic zine paint 0.00021 Carbon steel 0.02083 Air 0.00087 Concrete 3.94 3 Miscellaneous 6,088 Epoxy 0.00154 interior Concrete 1.10 concrete (1)
4. Primary Shield 1,813 Inorganic zine paint 0.00021 Carbon steel 0.05797 Air 0.00087 Concrete 9.0 Epoxy 0.00113
5. Sumps 209 Stainless steel 0.0158 Concrete 0.979 Carbon steel 0.0208 Air 0.00087

-- Concrete 6.5

6. Refueling 7,472(2) Stainless steel 0.02083 canal wall Air 0.00087 Concrete 4.24 Epoxy 0.00113
7. Miscellaneous 6,960.6 Epoxy 0.00113 Concrete 2.13 156/CAC COPATTA CONTAINENT HEAT SINKS HEAT TRANSFER WALL DESCRIPTION AREA (ft2 ) MATERIAL HIICKNESS (ft )
8. Miscellaneous 35,504.9 Epoxy 0.00154 interior Concrete 1.69 concrete (l) 9 Miscellaneous 1,010.2 Epoxy 0.00154 interior Concrete 6.01 concrete (l)
10. Refueling canal slab (3)
11. 171,132 Inorganic zine paint 0.00021 Struc{u[al steel 4/ Carbon steel 0.0161
12. Struc ural 44,536 Inorganic zine paint 0.00021 steel 4) Carbon steel 0.04913
13. Piping 147.726 Inorganic zine paint 0.00021 Carbon steel 0.030
14. Piping 35,976 Stainless steel 0.018
15. Piping (5)
16. --

13,700 Inorganic zine paint 0.00021 Mechanica}4) equipment Carbon steel 0.24 17.

Mechanica{4) equipment

18. Misce}4)lpneous steels 156/CAC COPATTA CONTAINMENT HEAT SINKS HEAT TRANSFER WALL DESCRIPTION AREA (ft2 ) MATERIAL THICKNESS (ft-)
19. Basemat 12,344 Epoxy 0.00154 Concrete 2.75 Air 0.00087 Inorganic zine paint 0.00021 Air 0.00087 Concrete 10.5
20. Reactor Cavity a) Walls 3,436 Inorganic zine paint 0.00021 Carbon steel 0.02083 Air 0.00087 Concrete 8.0 b) Cavity 708 Epoxy 0.00154 Bottom Concrete 1.0 Air 0.00087 Inorganic zine paint 0.00021 Carbon steel 0.0208 Air 0.00087 Concrete 8.0 NOTES:

(1) The 00PATTA input combined the miscellaneous interior concrete into 5 groups a.) < 36" thick b.) I 36" thick epoxy finish 0.5 mil c.) I 36" thick epoxy finish 18.5 mil d.) > 36" thick e.) > 36" tbick epoxy finish 18.5 mil (2) Both sides exposed to atmosphere (3) Included as part of item 6 '

(4) The 00PATTA input combined the miscellaneous structural steel into 3 groups a.) < 0.5" thick b.) 0.5" to 1.0" thick j c.) > 1.0" thick (5) Included as part of item 14 156/CAC  :

i

VEGP-ESAR-6 TABLE 6.2.1-5 THERMOPHYSICAL PROPERTIES OF CONTAINMENT HEAT SINKS Thermal Conductivity Volumetric Heat Capacity Material (Btu /h-ft- F) (Btu /ft' *F)

CO PA TTA CO PA TTA Paint 0.9 f. o 20.0 pg.

Carbon steel 28.0 35 52.5 5V Stainless steel 9.4 10 60.1 54 Concrete 0.65 09 28.8 G F.1 Galvanizing 64.8 47 5 40.9 54 Epoxy 0.97 1. 0 20.0 40 i

I Amend. 11 11/84

- - . m x ATTACHMENT 5 SEQUENCE OF EVENTS I

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TABLE 6.2.1-65

SUMMARY

OF RESULTS FOR MSLB CONTAINMENT PRESSURE - TEMPERATURE ANALYSIS sea x .

Power Brea k Max. Press. at - Vapor Temp. Dryout 5.8 psig 16.8 psi 9 24 psig Case Level Size Break Time (psig at Time Time at Time at Time at Time

] A (11 fftal Twee at Timal f *F at si fs1 (si fsi isi 1 102 Full Double ended 30.6 at 132 245 at 130 157 3.7 21.0 70.0 2 102 0.60 Double ended 28.4 at 1800 240 at 1800 366 21.0 110.0 220.0 3 102 0 90 SpIit 35.4 at 292 352 at 150 374 17.0 49.0 85.0 3

4 75 Full Double onded 30.8 at 158 245 at 170 195 3.5 21.5 70.0 5 75 0.55 Double ended 29.1 at 1800 242 a t 1800 516 25.0 131.0 260.0 6 75 0.84 Split 35.9 at 374 324 at the 448 15.5 48.0 88.0 i 7 50 Full Double ended 32.1 at 1800 248 at 1800 237 3.5 20.5 75.0 8 50 0.45 Double ended 31.7 at 1800 247 at 1800 476 29.0 170.0 350.0 9 50 0.80 Split 35.9 at 508 319 at 130 548 15.5 51.0 98.0 10 25 Full Double ended 30. 3 a t 1800 244 at 1800 207 3.8 18.1 70.0 11 25 0.33 Double ended 26.6 at 572 236 at 600 601 38.0 248.0 480.0 i

i 12 25 0.66 Split 33.6 at 398 308.7 at 130 572 18.0 64.0 131.0 13 HS Full Double ended 29.7 at 140 243 at 140 138 3.7 18.1 75.0 i

' 14 HS 0.2 Double ended 25.6 at 1517 235 at 1500 esA 10.5 55.0 72.0 15 MS 0.14 Split 41.9 at 1784 273 at 190 NA 33.0 167.0 390.0 %

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Su.mmneY 6 F COPATTA RESul.TS y

o l Case- hka Prus al m 4. s j No. Time (psi 3 a+ Ti-c) %p.c Temp a.1 Time *

(*F at s) i 1

27.6 a.} 12 2 465 af sig l 1 24.2 al sl9fo 297 al 260 l 3 29. I a+ AD4 819 el 234 1

4 .17 0 d 144 251 sk 13 3 i

5 34.5 a+ 445 ass at 400

(, 30.* a4 363 as9 a+ 230 7 A" I' *

  • 8 7 9 255 "I IIN g 4/,'.4 at 19oo 2 P4 a 4 455 9 49.T af 497 3 18 al 461 f, 45.7 = J- l 19 453 a e il J

,, 24.4 at it 40 ass =+ SGO

,, 21.5 a+ 322 312at320

,3 26.3 I 13 5 254 a l 133 4

,4 22.1 a4 !?oo 2 7a af 120 l g5 y/4 ak 1700 3 11 al 600 1

i

VEGP-FSAR-6 TABLE 6.2.1-68 SEQUENCE OF EVENTS FOR CASE 3 -

PEAK CALCULATED CONTAINMENT TEMPERATURE FOR MSLB foPATTA Time (s) Event 0 0.0 Break occurs, blowdown from all steam generators.

ff,g 16.5 Containment pressure setpoint for isolation at main feedwater lines reached (5.8 psig).

  1. 35 23.5 Main feedwater line isolation valves closed.

44 46.0 Containment pressure setpoint for isolation of main steam lines reached (16.8 psig).

53 53.0 Main steam line isolation valves closed, blowdown from broken loop steam generator and unisolated steam piping only.

.l

/ /J.7 60.0 Air coolers start.

/3/. 5 90.0 Containment pressure setpoint for actuation of (34 p;j) containment sprays reached (24 psig).

Jgg 150.0 Peak containment vapor temperature of 352.0'F is (319'F) reached.

225.5 190.0 Containment sprays start.

pgy,g 300.0 Peak containment pressure of 35.3 psig is reached.

3 446.0 Dryout occurs, blowdown equals auxiliary feedwater addition rate.

/ goo 1800.0 Auxiliary feedwater addition is terminated.

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