ML19308D694

ECCS Passive Heat Sink Data & Info.

ML19308D694
Person / Time
Site:	Crystal River
Issue date:	10/30/1975
From:	GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT
To:
Shared Package
ML19308D691	List: ML19308D690 ML19308D692 ML19308D694
References
GAI-1889, NUDOCS 8003120826
Download: ML19308D694 (21)

Text

.- -- . . _ . - ... - . -- . - . -.

j Riport Ns. 1889' 7

a

. I

ECCS PASSIVE HEAT SINK DATA AND INFORMATION l

l' 1

I

i j-6 i

Prepared by:

l 4-(

i Gilbert Associates, Inc. Q 525 Lancaster Avenue 0 Reading,'Pa. 19603 -8003120 L

h

, - - - - - - , -g -

, ,,,- - - , . . , , .t.--- n , rem-----*- ^

m.,,,,h,--m-ek.-n -m c,- ,-w,, - , - , , , +--- ,w-,

1 S CONTENTS Page,

1.0 INTRODUCTION

1 2.0 REQUESTS AND RESPONSES 2 2.1 New Free Containment Volume 2 2.2 Passive Heat Sinks 4 2.3 Starting Time of Containment Cooling Systems 10 2.4 Containraent Initial Conditions 14 2.5 Containment Spray Water Temperature 15 2.6 Fan-Cooler Heat Removal Rate 16

/ 2.7 Conclusion 18

3.0 REFERENCES

19 e

i t

ECCS PASSIVE HEAT SINK DATA AND INFORMATION

1.0 INTRODUCTION

This report presents the stammarised results of a detailed evaluation and calculation performed in response to the United States Nuclear Regulatory Commission (NRC) request for addition information dated August 12, 1975 relative to Crystal River Unit No. 3 Docket No.

50-302 ECCS parameters and comparison to referenced BAW-10103 Topical Report.

(

6 0

.- - , , , , ,, , , , , ,- - _ .. - . ,,e- - ,

2.0 NUCLEAR REGULATORY ComISSION ADDITIONAL INFORMATION REQUESTS AND ASSOCIATED RESPONSES AND ACKNOWLEDGEMENTS 2.1 Net Free Containment Volume - Justification should include the total gross internal containment volume and the internal structures and equipment and their volumes which are subtracted to obtain the net free containment volume. A discussion of the uncertainties should be provided, i

Response

Specific internal structures and equipment with their respective volumes, which were subtracted from the calculated internal containment volume of 2,337,910 ft3 to obtain the net free containment volume, are tabulated below. The volume

( of major structures, equipment and associated piping and valves were calculated in detail. For miscellaneous small pipe, valves, brackets etc. a factor of 10%

was added to the total major volume. As indicated by the tabulated results the calculated net free volume is less than the BAW 10103 value by 7.0%.

3 TABLE 2.1 NET FREE VOLUME - ft ft3 BARE PIPE 1,313 PAINTED PIPE . 1,194 INSULATED PIPE 4,634 INSULATION 3,126 R. C. PIPE 4,154 INSTRUMENTATION 83 PIPE HANGERS 267 DUCTWORK 1,700 INTERNAL CONCRETE 199,719 CARBON STEEL 4,663 STAINLESS STEEL 163 ELECT. TRAYS ETC. 623 R. C. SYSTEM 39,721 MISC. EQUIP., PIPES, ETC. = 26,000 TOTAL 287,360 ft3 CONTAINMENT GROSS VOLUME = 2,337,910 ft3

- 287,360 CONTADPfENT NET FREE VOLUME = 2,050,550 ft3 BAW-10103 VALVE 2,205,000 ft 3 i

'l

(_ .

i l

l .

4

.2.2 Passive Heat Sinks - Provide the actual passive heat oink structures for your plant. Discuas the method of determining the passive containment heat sinks. Identify each heat eink by category (i.e. , cable tray, equipment supports, floor grating, crane vall, etc.) and provide surface area, thickness, materials of construction, thermal conductivity and volumetric heat capacity, by component category used in the containment transient analysis code.

Response

The method of determining the passive containment heat sinks was by direct computation. (i.e. the actual dimensions of the equipment and structures were taken from scaled drawings and prints, this data was utilized to calculate the thickness and surface areas.) In the case where irregular shapes were encountered, conservative methods of estimating were used. As the portion of equipment and structures where estimating was required is, by percentage, s

very small the overall effect to the analysis is negligable. Appropriate Requirement Outlines were utilized in determining materials and paint specifications. The mil thicknees for paint applied to steel and concrete l

is considered conservative at 6 mil and 10 mil respectively.

Painted steel is carbon pipe and equipment that is not insulated. Bare (unpainted steel) is stainless steel pipe, equipment and only the external surface sheet of reflective metal insulation. The surface of the additional inner layers of insulation including that of the pipe or equipment covered by the insulation are neglected.

Table No. 2.1 below identifies each heat sink by category and indicates the respective surface area, thickness, material of construction, thermal conductivity l

and volumetric heat capacity.

- - - . n - - - - , , --, w

I .

TABLE NO. 2.2 FSAR VALUES SURFACE THERMAL HEAT ,

CATEGORY AREA THICKNESS MATERIAL CONDUCTIVITY CAPACITY ftf ft Btu /h-ft oF/ft Btu /ft2oF REACTOR BUILDINO 63,304 WALLS

a. Liner Plate .03125 Steel 26.0 58.80

b. Concrete 3.5 Concrete 0.45 22.62

c. Paint ,

.0005 Plasite 0.20 40.42 REACTOR BUILDING 18,138 DONE +

a. Liner Plate .03125 Steel 26.0 58.80 ,

b. Concrete 3.0 concrete 0.45 22.62

c. Paint .0005 Plasite 0.20 40 42 REACTOR BUILDING 105,941 Concrete 0.45 22.62 INTERNAL CONCRETE Paint .00083 Plasite 0.20 40.42 REACTOR BUILDING INTERNAL STEEL Framing, Equip.

& Pipe Restraints, Supports, Polar 149,335 .03122 Steel 26.0 58.80 '

Crane, Access Hatches, and Grating Paint .0005 Plasite 0.20 40.42

i .

TABLE NO. 2.2 (Cont'd)

FSAR VALUES SURFACE THERMAL HEAT CATEGORY AREA THICKNESS MATERIAL CONDUCTIVITY CAPACITY ftZ ft Btu /h-ft OF/ft Btu /ft Z *F Ventilating Duct -

Work, Reinforcing, 111,040 .00299 Steel 26.0 58.80 Hangers 20 gage (Inside

& Outside) .

Paint ---- .0005 Plasite 0.20 40.42 Instrtsments, Mounting

Brackets, Housings, 130 .0148 Steel 26.0 58.80 Valves and Tubing Paint -- .0005 Plasite 0.20 40.42 ,

Hangers and Supporting Steel 10,000 .0262 Steel 26.0 58.80 Paint - .0005 Plasite 0.20 40.42 Pipes & Valves &

Equipment 12,000 .0233 Steel 26.0 58.80 Paint .0005 Steel 26.0 58.80 Cable Trays, Conduit, Boxes, Penetration 45,820 .00625 Plasite 0.20 40.42 Enclosures ,

Paint 4

1 1

~

l TABLE NO. 2.2 (Cont'd)

FSAR VALUES SURFACE THERMAL HEAT CATEGORY AREA 'DIICKNESS MATERIAL CONDUCTIVITY CAPACITY ftZ, ft Btu /h-ft OF/ft Btu /ft 2OF REACTOR BUILDING INTERNAL STAINLESS STEEL Framing, Fuel Transfer Canal 9,361 .01563 Stainless 9.0 54.263 Liner Plate, Steel Sump Liner Plate Instruments, Mounting Brackets, 1,475 .0417 Stainless 9.0 54.263 Housings, Valves, Steel Tubing Pipes, Valves &

Equipment 11,000 .0676 Stainless 9.0 54.263 Steel Insulation 15,500 .00249 S tainless 9.0 54.263 Steel Cable Trays, Conduit, Boxes, 8,723 .00625 Stainless 9.0 54.263 Penetration Steel Enclosures u

g i

i

('

TABLE NO. 2.2A SUMERY i-A. The Reactor Building Walls including the concrete wall, steel lineri .

nnd paint:

Exposed area, f t 2 63,304 Paint thickness, ft 0.0005 Steel thickness, ft 0.03125 Concrete thickness, ft 3.5 B. The Reactor Building Dome including concrete, steel liner, and paint:

Exposed area, f t 2 18,138 Paint thickness, ft 0.0005 t

Steel thickness, ft 0.03125 Concrete thickness, ft 3.0 C. Painted internal steel:

Exposed area, ft 2 409.817 Paint. thickness, f t 0.0005 Steel thickness, ft (REF. TABLE NO. 2.2)

D. Unpainted internal stainless steel including outer layer of stainless steel insulation with an area of 15,500 ft2 and a thickness of 0.00249 (Ref. Table 2.2) .

- Exposed area, f t 2 46,059 Thickness (REF. TABLE NO. 2.2)

9 I'

E. Internal Cone.. 2te:

Exposed area, ft 2 105,941 .

Paint thickness, ft 0.00083 Concrete thickness, fe 1.435 (FSAR)

/

.. .- =

10 i 2.3 Startina Time of Containment Coolina System (s) - Discuss the factors that show that the start time (s) assumed in the containment response analysis represent the earliest possible initiation of system (s) operation.

Response

BUILDING SPRAY SYSTEM

', 1. Reactor building spray pump start will not occur until two i conditions have been met:

a) 30 psig pressure exists in containment

, b) Block 4 of the diesel loading sequence must have been

[ loaded resulting from either 4 psig containment pressure 59; RC pressure < 500 psig fut RC pressure < 1500 psig.

i Time required for a): If all instrumentation error was in the conservative direction, actuation would be initiated at 26.6 psig.

(The pressure switches will be calibrated to 28.5 psig, +0, -0.5 to insure actuation by 30 psig). All FSAR figures were therefore checked for the shortest time required to reach 26.6 psig. This is found to be 3.6 seconds from FSAR Figure 14-72B.

Time required for b): The controlling parameter is reactor building pressure. It will take at least 20 seconds for any size break documented in the FSAR to result in RC pressure

. dropping to 1500 psig, and even longer to reach 500 psig.

However, a containment pressure of 4 psig will occur in less than a second and will therefore be the cause of E. S.

11 i actuation and initiation of the timing cequence. Considering calibration set point (3.25 psig, +0, -0.15) and total potential

,. instrument loop error (10.66 psig), the ' earliest actuation vould occur at 3.25 psig -0315 - 0.66 = 2.44 psig. FSAR Figure 14-72B indicates the quickest achievement of this pressure: 0.3 seconds. This would result in block loading with BS pump actuation fif teen (15) seconds later. If an undervoltage condition occurs simultaneously, block loading will not start until the emergency diesels are operating. The diesels are required to start in 10 seconds or less, and field tests on this type of diesel have indicated starting times of 7.5 seconds.

Conclusion i Building spray pumps will not start utstil the E. S. block loading sequence is timed out, which will require a minimum total time of 15.3 seconds af ter the LOCA if normal AC power is available, or 22.8 seconds if the diesels are required as compared to BAW-10103 of 2.4 seconds.

2. Air Handling Recirculation and Cooling Units The only requirement for AHF-1A, IB, & IC to be operating in 1

the E. S. mode is that block 2 of the diesel loading sequence ,

l has been accomplished. When b1Giu. 2 ts headed, all three fans  !

l 1

will go on low speed operata c. ifclation of block loading j will be 0.3 seconds as in 1 (b) above, and On additional 5

12

( second time delay occurs before block 2 is loaded. An undervoltage condition would have the same effect as described in 1 (b)~above.

Conclusion Air handling fans will initiate containment cooling in a minimum of 5.3 seconds if normal AC power is available, or 12.5 seconds if diesels are required as compared to BAW-10103 of no delay.

All times are based on the worst case LOCA documented in the FSAR.

A breakdown of the starting time, which yields the quickest activation time for the spray systems is shown below:

( Normal AC Power Available 0 0.3 10.3 ESF MOVs D21ay Open 10s (a) 5.3 15.3 BS Pumps 25.3 BS Header Full 68.5 at. 100% Spee_d ,

5s 15 3 lo s(a) 43.273 BS System O.3 AHF BS Pumps Starts Start Operational Time, Second Block 2 -

+

13 I Diesels Required 11 7.8 17.8 ESF MOVs Dmlay , _

,Open Diesel 103 (a)

Start 0.3 Delay 7.8 12.8 22.8 BS Pumps 32.8 BS Header Full 76.04

at 100% Soced 7 7 5 lo s los(a) 43.24 s 7.5, Diesel s AHF BS Pumps BS System 0.3 Start Start Start Operational Block 2 Time, Second (a) Assumed Value (Conservative)

Note: The above illustrated times are in excess of those asstmed in the containment response analysis (Ref.

BAW-10103).

14 2.4 Containment Initial conditions - Compare the initial values of temperature, pressure and relative humidity in the containment with the range of values that will be permitted during plant operation.

Response

INITIAL VALUES TEMPERATURE PRESSURE RELATIVE HUMIDITY 1100 F 13.7 psia 100%

PERMISSABLE OPERATING VALUES TEMPERATURE PRESSURE RELATIVE HUMIDITY 90 F - 130 F(b). 12.7 - 17.7 psia 0% - 100%

(

4 (b) Anticipated Value (Conservative) l

.n

,e -

15 2.5 Containment Spray Water Temperature - Show that the value of containment spray water temperature used in the containment response analysis is the lower bound temperature consistent with the plant operating conditions and that the spray flow rate used is suitably conservative.

Response

The Borated Water Storage Tank, Sodium Thiosulfate Storage Tank and Sodium Hydroxide Storage Tank are continually and redundantly heated by submersive type heaters or tank heat tracing. The containment spray water temperature used in BAW-10103 report is 40 F. The containment spray water temperature relative to Crystal River Unit No. 3 is as follows:

Borated Sodium Sodium

k. Water Thiosulfate Hydroxide 70 F 50 F 75 F This results in a conservative final containment spray temperature of approximately 69 F.

The spray flow rate used in BAW-10103 is 1,800 gpm which is approaching pump runout conditions. The spray system flow rate for Crystal River Unit No. 3 is designe'd at 1,500 gpm which is suitably conservative.

i 1

(.  !

1

16 2.6 Fan-Cooler Heat Removal Rate - Compare the maximum fan-cooler heat removal rate for Crystal River, Unit 3 with that assumed in BAW-10103. Show that minimum operational values of service water temperature have been used.

Response

-The total fan cooler heat removal rate (HR) as presented in BAW-10103 is a function of reactor building atmosphere temperature, i.e.

HR(BTU /S) = 3.0(0.9T2 -76.9T + 1670)

Imputting CR-3 Reactor Building design temperature of 2810F illustrates that BAW-10103 assumed heat removal (HR) rate is greater than CR-3 plant actual.

( Example: BAW-10103 (HR)

HR(BTU /S) = 3.0[0.9(281)2-76.9(281) + 1670]  ;

HR(BTU /S) = 153,378 TOTAL CRYSTAL. RIVER UNIT No. 3 (HR)

HR(BTU /M) = 80 x 106 / UNIT = 2.4 x 108 TOTAL HR(BTU /S) = 66,666 TOTAL Based on 105 F cooling water.

This heat removal (HR) rate modified to 800 F cooling water equals approximately HR(BTU /S) = 79,000 TOTAL

17

+

The service water temperature used in BAW-10103 report is 400F. Due to the global location of Crystal River Unit No. 3 the fan cooler design is based

- on 800F, therefore, the input of 40 F utilized in BAW-10103 is considered very conservative.

(.

?

18

[~'

2.7

Conclusion:

The ECCS parameters discussed in this report, with the exception of equipment and structure surface area, are more conservative than those used in the generic evaluation of BAW-10103. Note that although the energy absorption capacity is relatively low, the surface area as calculated in this report included both sides of small gage steel such as cable trays, tray hanger, conduit hanger, etc. and thin plate stainless such as fuel transfer canal liner plate, sump liner plate, stainless steel insulation, etc. This inside, outside and thin plate aurface area calculation method amounts to approximately 87,000 2ft ot painted steel and 28,000 ft 2 of stainless steel. Consideration of this method a' :::;ut?rion

( results in (409,817 ft2 - 87,000 ft2 ) a total of 322,817 ft2 of painted areel and (46,059 ft2 - 28,000 ft 2) a total of 18,059 ft2 of stainless steel. Hence, although the actual surface area exceeds -

BAW-10103 values the overall thickness are significantly less thus providing & certain amount of conservatism within this parameter.

\w

d*

19 3.0- REFERENCES

1. United States Nuclear Regulatory Commission's Request for additional information (ECCS), dated August 12, 1975 4

2. Babcock and Wilcox Topical Report BAW-10103 dated September 1975

3. FINAL SAFETY ANALYSIS REPORT, Crystal River Unit No. 3 Docket No. 50-302 N

i i

I l

l I

l l

A_.

, __ _ . -_ . -, - . _ _ . - <