ML20210P584

Forwards Description of Facility Cooler Sys & Simulation in 1/4 Scale Test Facility,Addressing Last Open Question on 1/4 Scale Test Facility & Closing Subtask 9.5 of Hydrogen Control Program Plan.W/One Oversize Figure

ML20210P584
Person / Time
Site:	River Bend
Issue date:	07/30/1986
From:	Langley J HYDROGEN CONTROL OWNERS GROUP
To:	Bernero R Office of Nuclear Reactor Regulation
References
HGN-101, NUDOCS 8610060802
Download: ML20210P584 (14)

Text

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MARK Ill CONTAINMENT HYDROGEN CONTROL OWNERS GROUP j. n. tongiey. Project Manager c/o Gulf States Utilities . North Access Rood at Highway 61 . St. Froncisville, LA 70775 504 635 6094 Ext. 2832 July 30, 1986 IIGN-101 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Robert Bernero

Subject:

River Bend Station Unit Coolers During the November 20, 1985 meeting held between the Ilydrogen Control Owners Group (llCOG) and the Nuclear Regulatory Commission, llCOG agraed to provide information concerning the River Bend Station unit coolers. Attached is a description of both the River Bend Station unit cooler system and its simulation in the 1/4 scale test facility.

Please note that submittal of this document addresses the last open question on the 1/4 scale test facility and constitutes closure of Subtask 9.5 of the IICOG llydrogen Control Program Plan.

This submittal was compiled by llCOG from the best information available for submittal to the Nuclear Regulatory Commission. The submittal is believed to be complete and accurate, but it is not submitted on any specific plant docket. The information contained in this letter and its attachments should not be used for evaluation of any specific plant unless the information has been endorsed by the appropriate member utility, ilCOG members may individually reference this letter in whole or in part as being applicable to their specific plants.

Very truly yours, J. R. L 'y Project Manager JRL/jlw Attachment 0T cc: see attached list G0 i I \

8610060802 860730 PDR ADOCK 00000458 p PDR-

Page 2 of 2 t HGN-101 cc:e Hrg Lester;L.EKintner~ % <,

liydrogen Control Project Manager U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation

! Washington, D. C. 20555 i

Mr. J. Kudrick Plant Systems Branch Division of BWR Licensing Office of Nuclear Reactor Regulation Washington, D. C. 20555 Dr. R. W. Ilouston Deputy Director, Division of BWR Licensing U. S. Nuclear Regulatory Commission t Office of Nuclear Reactor Regulation i

Washington, D. C. 20555 i

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Attachment to IIGN-101 River Bend Station Unit Cooler System Simulatibn in the 1/4 Scale Test Facility i

i Introduction i

The Hydrogen Control Owners Group (HCOG) has implemented an extensive program of testing and analysis to quantify the effects of hydrogen combustion following a hydrogen generation event (HGE). As part of this program, combustion testing is being performed at the HCOG Quarter Scale Test Facility (QSTF).

This testing is intended to account for plant specific design features which would mitigate or affect the consequences of hydrogen combustion. Since containment unit coolers are unique mitigative

, features to River Bend Station (RBS), they have been incorporated into the QSTF design for use during River Bend plant specific testing. This report discusses the RBS containment unit cooler design and operation and the QSTP simulation of the RBS unit coolers.

RBS Design and Operation Three containment unit coolers are provided in the RBS design. Two of the three 50% capacity containment unit coolers (lHUR*UCIA, IB) are safety related and are sized for normal operating conditions.

The third unit cooler (lHUR-UCIC) is non-safety related and is used during normal operation only. During normal operation, the coolers are supplied with coolant from the chilled water system.- During accident conditions, standby service water at a maximum temperature of 95"F and a flow rate of 540 gpm through each safety related cooler is used for cooling water. Each cooling unit has a local intake and discharges to a common ventilation distribution ductwork system which routes the cooling air throughout the containment. A pressure relief damper is installed in the ductwork between the two safety related unit coolers to protect the ductwork during design basis accidents. This relief damper opens inward when the pressure differential across the ductwork is greater than or -e qual to 15 i inches of water. Containment unit coolers A and B are powered from independent 480VAC standby buses and are automatically deenergized for load sequencing following an automatic start of the emergency diesel generators. Thus, at least one containment unit cooler is i available if either standby diesel generator fails to start. The

containment unit coolers are automatically initiated on high I

containment pressure with an interlock to delay initiation until 10 minutes after the high drywell pressure signal.

During LOCA conditions the heat removal rate for each unit cooler is 23,000,000 Btu /hr at a 185 F dry bulb temperature and 100% relative humidity while supplied with maximum temperature 95 F ctandby 4

service water. The containment air recirculation cooling system is shown in figure 1 and design data of the principal components are listed in Table 1. Each safety related containment unit cooler consists of the following components:

1. Fan / Motor Assembly Each unit cooler has a statically and dynamically balanced non-overloading vaneaxial type fan. Each fan is directly driven by a totally enclosed, singlespeed, air-cooled motor.

The motor is seismically and environmentally qualified as discussed in Section 3.11 of the RBS FSAR.

2. Cooling Coils Finned tube cooling coils remove heat from the containment air. During normal operation, the main mode of heat transfer is sensible cooling whereas during post-LOCA operation, condennation is dominant. The cooling coils are designed for optimum tube and fin spacing and proper drainage to avoid water clogging during post-LOCA operation. Drain pans are provided to collect and remove the condensate. Cooling coil construction conforms to the requirements of ASME code,Section III, Class 3, and bears the "N" stamp. Cooling coil framing and supports conform to the requirements of subsection NF of ASME code,Section III.

The unit coolers discharge air directly into the shielded compartments within the containment. Gravity dampers located in the discharge duct of each cooler are normally closed when the fan is not running. These dampers open under fan discharge pressure but close on reverse flow to prevent backflow through the fan.

Discharge points and flow rates for the reactor plant ventilation system are given in Table 2.

Quarter Scale Modeling The modeling of the RBS Reactor Plant Ventilation System for the Hydrogen Control Owners Group (IICOG) Quarter Scale Test Facility (QSTF) is based on Froude scaling of the design air flow rates and total cooling capacity. The Froude scaling relationships are applicable as follows:

Volumetre flow varies as (1/4) 5/2 Length varies as 1/4 Velocity varies as (1/4) 1/2 Based on these relationships, the QSTP design parameters given in Table 3 were developed. Due to the large number of vents in the RBS design, a simplified design was used in the QSTF model while maintaining the same overall air flow distribution. Selection of vent sizes and locations for the QSTF were based on criteria which allow for preservation of the air flow distribution while reducing the number of vents required in the model. The criteria used in the selection process are follows:

1) The number of vents in the actual plant (70) should be reduced to 20-25 vents at quarter scale.

2) Scaled total volumetric flow should be preserved.

3) Air flow distribution will be maintained by; a) Division of containment volume into zones (below 114',

114' to 141', 141' to 162'-3", 162'-3" to 186'-3",

186'-3" and above, full scale).

b) Combination of vents within zones.

c) Combination of vents within a quadrant.

d) Preservation of vents which discharge toward the suppression pool surface from the HCU floor, e) Inclusion in model of flow for narrow passages (i.e.,

270 azimuth for full scale plant).

4) Vents located in rooms in the actual plant will be included in the QSTF simulation by having vents discharge ^from the QSTF enclosed volumes. Discharges from enclosed volumes are given in Table 4.

5) QSTF is mirror-image (about the 0-180 axis) of RBS.

6) The exit velocity for QSTF vents that represents a ,

combination of actual plant vents should be equal to the '

scaled avera8e velocity of the vents combined.

The QSTF air distribution system is therefore based on 5 levels, four quadrants, and vents for narrow passages. The location of the QSTF vents and the flow rate are given in Table 5. Figure 2 shows the location of the vents and associnted ductwork. The henL exchanger and fan required to simulate the unit coolers were selected to provide the required airflow and heat removal capacity based on worst case RBS design values.

During the RBS QSTF tests, operation of the cooling system will be consistent with the prototypical procedures. In addition, a test will be performed with a simulated relief damper open to evaluate the effect of local discharge from the unit coolers, l

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1 Conclusion i The RBS reactor building ventilation system has been adequately j simulated in the QSTF. The air distribution system is adequate i since the volumetric flows in each sector of the test volume correspond to the flows in the actual plant. Also, the total

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i volumetric flow and heat removal capacity have been scaled appropriately. The cooling system will be operated during all RBS

-QSTF testing in accordance with unit cooler operation at the prototype.

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Table 1 DESIGN DATA FOR REACTOR BUILDING VENTILATION SYSTEM

1. Containment Ventilation System Design Data Containment unit coolers Equipment Mark No. lilVR*UCIA, IB

& lilVR-UCIC Each containment unit cooler

consists of the following components

Filters Type Disposable, fiberglass i Airflow capacity, cfm 50,000

Filter pressure drop (dirty),

in W.G. 0.50 Face velocity (max), fpm 480 i Filter Efficiency (average)

ASIIRAE 52-68 20 4

) Cooling coils Design pressure, psig 200 j Design temperature, F 100 Type Chilled water, normal "

service water, LOCA*

i Total cooling capacity, j normal, mbh 2,543 LOCA, mbh 23,000*

Flow rate normal, gpm 350 LOCA, gpm 540*

Supply air fan

Type Vaneaxial

, Airflow capacity, cfm 50,000

Total pressure capability, in W.G. 7.5 Speed, rpm 1,750

Motor, hp 150 Type of discharge llorizontal

• 111VR*UCl A , 1 B i

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Table 2  !

REACTOR PIANE VENTIIATION SYSTEM AIR DISTRIBUTION Location Description of Flowrate Exit (Azinuth, Radius) Elevaticm (ft) (cfht (sq ft) Release Point El 186'-3" 204'-3" 2400 4.5 45 off liner - H (139,, 56') 2400 4.5 45 off liner - H (131 , 56') 204'-3" (135 , 55') 199'-9" 3000 5.0 Facing in toward

-H (26 , 55'-8") 195'-9" 2400 4.5 4 off liner - H (32 , 55'-8") 195'-9" 2400 4.5 4 off liner - H (29 , 54'-8") 199'-6" 3000 5.0 Facing in toward rgactor - H (24 o, 55'-10") 195'-9" 2400 4.5 45 cff liner - H (23 , 55'-10") 195'-9" 2400 4.5 45 off liner - H (24 , 54'-10") 199'-6" 3000 5.0 Facing in toward

-H (318 , 55'-10") 195'-9" 2400 4.5 4 off liner - H (326 , 55'-10") 195'-9" 2400 4.5 4 off liner - H (322 , 54'-10") 199'-6" 3000 5.0 Facing in toward reactor - H El 162'-3" (95 6 26'-6") 182' 200 0.42 Valve room - H 26'-6") 182' 200 0.42 Valve room - H (10g (99 , ,23') 171'-1" 300 0.33 cont storage roczn - V - down (33 , 44'-6") 170'-1" 500 1.25 Gen area - H (37 , 43'-6") 170'-1" 500 1.25 Gen area - H (99 , 41') 170'-8" 1200 4.5 Gen area - V -

down (107 , 39') 170'-8" 800 3.0 Gen area - V -

down (13 , 48') .171'-1" 1000 2.0 Gen' area - H

, 48'-6") 168'-8" 1000 2.78 Elev mach rocan - H (1 RWCU ht exch room - H 177'-3" 1770 3.0 (1(,

(1 , 51')

51') 163'-9" 1200 2.25 RWCU ht exch roczn - H 51') 152'-6" 1200 2.25 RWCU ht exch roczn - H (17 (338 , 57'-6") 174'-4" 660 1.5 Gen area - V - down (304 , 33') 174'-6" 670 1.5 Gen area - H (304 , 52') 170'-6" 680 1.5 Gen area - H (270 , 56') 174'-6" 500 1.0 Gen area - V- down (254 , 51'-6") 176'-9" 270 0.5 Gen area - H (249 , 42'-6") 174'-6" 350 0.5 Valve nest - H (238 , 30') 174'-7" 75 0.17 Flt denin room - H

Table 2 (Cont.)

Iccation Flowrata Exit Description of (Azlanth, Radius) Elevation (ft) (cfht (sq ft) Release Point j (275 , 22'-10") 174'-7" 75 0.17 Fit domin reau - H (238.5 , 43'-6") 174'-6" 480 1.0 Gen area - V - down (216 5 , 43'-6") 171'-2" 500 1.0 Gen area - H l

(2123 , 44'-6")

l 169'-7" 500 1.0 Gen area - H El 141'-0" i (115 , 47'-6") 150'-8" 6000 6.0 Gen area - H (1240 , 149'-2" 800 1.0 Gen area - H (13g.5,47'),51'-6") 154' 1000 1.67' Gen area - H (34 48'-6") 151'-5" 520 1.25 Gen area - H (546 5 , 48'-6") 148'-5" 800 3.0 Gen area - V - down (63 51') 148'-5" 1200 4.5 Gen area - V - down (30 , 43') 149'-10" 3000 5.8 Gen area - H (30 , 48'-6") 151' 3000 6.0 Gen area - H, (29 , 43'-6") 149' 500 1.0 PMCU punp roan - H l (29 , 55'-6") 154' 1200 3.0 Gen area - H '

(24 , 55') 157'-5" _850 1.75 Gen ama - H (24 , 40'-6") 157'-5" 800 1.75 RNCU waste revery (218 , 44') tank - H 149'-7" 850 1.75 Gen area - H (212 , 44'-6") down 155'-3" 850 1.75 Gen area - H El 114'-0" ,

, (16.5 , 51') 125'-6" 1000 1.5 (16 5 , 51') Sta tunnel - H 118'-8" 1000 1.5 Sta tunnel - H (44 , 49') 135'-6" 920 2.25 Gen area - V - down (56 , 43'-6") 123'-4" 1550 2.22 Gen area - H (58 , 44'-6") 135'-4" 1200 2.33 Gen area - H (60 44') 124'-8" 1200 1.94 Gen area - H (120 , 43'-6") 125'-1" 1000 1.75 Gen area - H (121 , 43'-6") 135'-3" 1000 1.67 (125 , 43'-6") Gen area - H 127'-5' 930 1.0 Gen area - H (306,, 47') 132'-8" 1270 2.89 (300 5 , 52'-6") Gen area - H

.123'-2" 1270 2.89 (2973 , 45') 134'-9" 1200 2.53 Gen area - H (2943 5 , 51'-6") Gen area - H 125'-1" 1130 2.53 Gen area - H (246 , 51'-6") 125'-2" 730 1.5 Gen" area - H (24 5 , 49'-6") 135'-8" 730 1.5 Gen area - H (21 , 45'-6) 1365-0" 470- 1.0 (208 , 51'-6") Gen area - V - down 121'-11" 500 0.97 Gen area - H (243.5 , 52') 114'-0" 3910 2.25 Gen area - V - down (296 , 60') W grating 114'-0" 3910 2.25 Gen area - V - down W grating (123 , 43'-6") 114'-0" 3910 1.94 Gen area - V - down (57.5 , 43'-6") W grating i

114'-0" 3910 2.25 Gen area - V - down W grating i

Table 3 QSTF SIMULATION DESIGN DATA l

l Full Scale 1/4 Scale a

i Air Flow (cfm) 50,000 1560 i Water Flow (gpm) 540 17* ,

95 95**

Water Temperature lleat Transfer Ares (ft ( F)2) 1752 110*

Cooling Capacity (Btu /hr) 23,000,000 720,000 1

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• Accurate modeling of these parameters is not required as long as i accurate modeling of airflow and cooling capacity is provided.

l ** Water temperature will be field adjusted to provide accurate simulation of airflow and heat removal t

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l Table 4 l AIR DISCilARGE FROM ENCLOSED AREAS i

i RBS Enclosed Area QSTF Exit Location j

i Steam Tunnel At containment wall upward from j botton of steam tunnel i

Valve Evaluation 162.3' radially outward from inner wall, azimuth 99 Contaminated Storage Same as valve room l Room i

RWCU lix Room Elevation 162'-3" radially outward at 17" azimuth Filter Demineralizer Elevation 170' radially outward i

Room i

i RWCU Pump Room Elevation 141' radially outward at 230 azimuth i

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i Table 5 QSTF Vents

Location Vent no. Azimuth Radius Elevation Flow rate Exitgrea (ft) (ft) (cfm) (ft )

4 1 225 14.0 33.1 122 0.875 2 331 13.8 31.7 122 0.875

3 119 13.9 31.7 122 0.875 i

4 38 13.9 31.7 i

122 0.875 i

5 245 10.9 24.6 73.4 0.901 6 340 10.3 23.4 80.8 0.808 7 45 11.9 l 25.6 31.4- 0.282

8 102 12.4 26.1 19.8 0.142

9 137 11.0 25.3 23.3 i

0.188

! 10 a

242 12.0' 19.7 121.9 0.542 11 305 12.4 19.2 39.4 0.547 i

12 56 11.5 19.6 93.6 0.738 l

13 139 10.6 18.8 i

46.9 0.384 14 103 13.9 20.9 32.0 0.297 15 311 11.5 14.2 91.7 0.659 16 238 10.9 14.4 1

45.8 0.276 17 61 12.3 14.4 91.7 0.817 i

18 129 12.5 14.5 38.0 0.312 1

19 116 13.0 10.6 61.1 0.141 20 64 15.0 10.6 61.1 0.141 21 2'17" 10.9 10.6 61.1 0.121 22 302 10.9 10.6 61.1 0.141 1

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