ML19326C670
| ML19326C670 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/15/1975 |
| From: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19326C671 | List: |
| References | |
| 12155, NUDOCS 8004250488 | |
| Download: ML19326C670 (14) | |
Text
_ _ - _
NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL n#
- (TEMPORARY FORM) 1 CONTROL NO: / 2 I M FILE:
FROM: Arkan m P'.r ti Light Co DATE OF DOC DATE REC'D LTR TWX RPT OTHER Little Rock, Ark 10-15-75 10-20-75 L *.-.
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3.,... 4 TO:
ORIG CC OTHER SENT NRC PDR MX Mr zieninn ene sic;ned SENT LOCAL PDR 2
CLASS I UNCLASS ~
PROPINFO INPUT NO CYS REC'D DOCKET NO:
XEEE 1
50-313 DESCRIPTION:
ENCLOSURES:
Ltr re our 9-16-75 Itr....tran: the follow:
A.idi'-ion 21 info concerning re teter buildin7 preccure rernonsa relativa to ECCC performance
' ACKNOWLEDGED DO NOT REMOVE THIS DOCUMENT C0llTAINS PLANT N AME: Arh an.uc 01 P00R QUAUTY PAGES FOR ACTION /INFCRMATION in.cn.7s ev BUTLER (L)
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M8(o M. DUNCAN M EXTEaNAL DISTRIBUTION 1 - LOCAL POR Ao n s <Ilus llu, ArW 7f1 - TIC (ABERNATHY) (1)(2)(10) - N ATIONAL LABS 1 - PD R-SAN /LA/NY fl - NSIC (BUCHANAN) 1 - W. PENNINGTON, Rrn E 201 GT 1 - BROOKHAVEN NAT LAB 1 - ASLB 1 - CONSU LTANTS 1 -- G. ULRIKSON ORN L 1 - Newton Anderson
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H 2LPl N O UUlLO ARKANSAS A RK ANS AS POWER G LIGH T COMPA NY GTH G LOUlGl A14 A ST AEETS. LITTLE ACCK. A AK ANS AS 72203. t5013 371-40C0 October 15, 1975 Director of Nuclear Reactor Regulation Attn:
Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Arkansas Power 6 Light Company Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Re-Evaluation of ECCS Per ormance f
Dear Mr. Ziemann:
Your letter of September 16, 1975 to Mr. J. D. Phillips requested additional information concerning reactor building pressure response relative to the above subj ect. Attached find our responses to those items.
As stated in our initial submittal of July 9,1975, your expeditious review, comments and/or approval is requested.
Ve y truly yours,
-,c William Cavanaugh III Manager, Nuclear Serv es NC: RMC:jp
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1.
NET FREE CONTAINMENT VOLUME The total. net free containment volume of 1,865,590 cubic feet was obtained by subtracting the total occupied volume from the gross volume as follows:
Gross Volume 2,080,800 cu. ft.
Occupied Volume Concrete 162,500 cu. ft.
Equipment 36,860 cu. ft.
Vent. Equipment 650 cu. ft.
R. C. Piping 2,900 cu. ft.
Misc. Piping 8,300 cu. ft.
Struct. Steel 4,000 cu. ft.
Total Occupied Volume 215,210 cu. ft.
Net Free Volume 1,865,590 cu. ft.
The gross volume is calculated based on internal reactor building dimen-sions. Occupied volume is calculated based on the conservative assumption that all equipment and structures within the reactor building are solid mas ses. As an additional conservatism, the volume displaced by the reactor ' coolant prior to the LOCA is included as occupied volume rather than free volume.
Although the free volume cannot be determined precisely due to the complexity of int'ernal component arrangements, any error in this calculation will not be large enough to have a significant effect on the reactor building pressure analysis. The uncertainty in the method -
has oeen estimated to be less than 0.5% of the free volume or 10,000 cubic feet.
s 2.
PASSIVE !! EAT SINKS lleat sink geometric data and thermodynamic properties for Arkansas Nuclear One-Unit I are presented in the following tables.
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HEAT SINK GEOMETRIC DATA Thickness Surface Area Heat Sink (inches)
Square Feet 1.
Containment Walls Coating-(Type B)
.008 25,000 Carbon Steel Liner Plate
.25 Concrete 45.0 2.
Containment Walls Coating (Type A)
.006 40,000 Carbon Steel Liner Plate and Stiffeners
.25 Concrete 45.0 3.
Containment' Dome
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Coating (Type A)
.006 15,500 Carbon Steel Liner Plate and Stiffeners
.25 Concrete 39.0 4.
Steel Floor Grating Coating (Type A)
.006 15,200 Carbon-Steel
.250*
s Coating (Type B)
.008 14,500 L5.. Structural Steel Coating (Type A)
.006 14,000
' Carbon Steel
.750 Coating (Type B)
.008 11,000 6.
Elevator Siding Galvanized Coating
.001 6,000 Carbon Steel
.036
.7.
' Refueling Canal.
Stainless Steel Liner Plate
-.183 7,300 Concrete 60.0 7,300
~8.
_: Coated' Concrete Walls Coating (Type C)
.130
-Concrete 33.0
- 504 32.0
- 1,176
- 9.. Uncoated Concrete' Walls (Primary Shield).
48.0
- 71,300
~ Concrete
~36.0 5,200 18.0
- 1,078
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i Thickness Surface Area Heat Sink.
(inches)
Square Feet 10.
Base Slab Coating (Type C)
.130 3,900 Carbon Steel Liner Plate (l' Below Concrete)
.250 Concrete 108.000 t
-11.
Elevated Floor Slabs 9
Coating.(Type C)
.130 4,130 Concrete 24.000*
'12.
Prirary Shield Wall Coating (Type B)
.008 2,000 Concrete 36.0 Carbon Steel Liner Plate 0.25 13.
Elevated Floor Slabs Coating (Type'C)
.130 1,422 Concrete 18.0
- 14.
Elevated Floor Slabs I
Coating (Type C)
.130 3,400 Concrete 10.00 *
' 15.
Pol'ar Crane Steel Coating (Type-D)
.010 1,470 Carbon Steel
.183*
-16.
Polar Crane Steel Coating (Type D)
.010 80 Carbon Steel
.25 *
- 17. -Polar. Crane Steel.
Coating :(Type D)
.010 145 Carbon Steel'
.312*
18 '.
Polar Crane: Steel
' Coating-(Type D)
.010 4~,560
~ Carbon Steel
.375*
'19.
. Polar Crane. Steel
' Coating.(Type D)
.010 895
. Carbon Steel
.500*
20.
Polar Crane Steel Coating (Type D)'.
.010 550 Carbon Steel
.625*
21.
Polar Crane Steel Coating (Type D)
.010 455 Carbon Steel-
.750*
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Thickness Surface Area Heat Sink (inches)
Square Feet 22.
Polar Crane Steel Coating (Type D)
.010 17 Carbon Steel
.875*
23.
Polar Crane Steel Coating (Type D)
.010 865 Carbon Steel 1.000*
24.
Polar Crane Steel Coating (Type D)
.010 140 Carbon Steel 1.25
- 25.
Polar Crane Steel Coating (Type D)
.010 1,020 Carbon Steel 1.50
- 26.
Polar Crane Steel Coating (Type D)
.010 765 Carbon Steel 1.75
- 27.
Polar Crane Steel Coating (Type D)
.010 2
Carbon Steel 2.00
- 28.
Tie Rods
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Coating (Type A)
.006 1,470 Carbon Steel 3.0
- 29.
Main Steam Pipe Restraint Steel Coating (Type A)
.006 1,500 Carbon Steel 1.75
- 30.
RCP & S.G. Restraint Steel Coating (Type A)
.006 7,700 Carbon Steel 2.0 31.
Miscellaneous Restrait.ts Coating (Type A)
.006 1,320 Coating (Type B)
.008 1,740 Carbon Steel 0.25
- 32.
Polar Crane Walkway Plate Steel Coating (Type A)
.006 3,000 Carbon Steel
.250*
33.
Polar Crane Rail Support Steel Coating (Type A)
.006 8,000 Carbon Steel 1.0
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Thickness Surface Area Heat Sink (inches)-
Square Feet I
. 34.
Cable Trays Calvanized coating
.001 7,860
-Carbon Steel
.100*
- 35.. Electrical Conduit
.Calvanized Coating
.001 8,500
. Carbon Steel
.176*
36.
HVAC Ducts Galvanized' Coating
.001 44,400 i
~ Carbon Steel
.100 t
37.
Core Flood Tanks
'S. S. Cladding ~
.125 1,630 Carbon Steel' 2.25 a
38.
Seal Plate Stainless Steel' 1.00
- 185 39.-
Reactor Coolant Ouench Tank 1
Stainless Steel ~
.375 630 a
40.
Transfer Tube Blind Flange Stainless Steel 2.125 8
41.
Exposed Transfer Tube Stainless Steel
.375 36 i
i 42.
Incore Instrument Tank Cylindrical (S.S.)
.375 1,055 Base Plate (C.S.)
2.625 154~
S. S. Cladding
.125
'154 e,
43.
Fuel' Transfer Mechanism Stainless Steel
.25
- 30 44.-
Uninsulated_ Steel Pipe Stainless Steel
.120 1,457
.134 648
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.148 '
1,205
.165 11
.216 73
.250 45
.280 245
.375 210
.438 73 1.125 695 Carbon Steel
.216-
-110
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'" ~
.237-600
.280
-785-
- These, sinks are exposed on both sides', therefore for containment i
i pressure response
- analyses average half thickness should be used in lieu of these total thicknesses.-
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HEAT SINK THERMODYNAMIC DATA MATERIAL PROPERTIES Thermal Specific Heat Conductivity.
Material (BTU /cu ft-F)
(BTU /hr-ft-F)
Carbon Steel-56 26
-Concrete-
' 30 -
0.9
' Stainless Steel-55.7 10 Coating Type Description A
3 mils Carbozine 11+
3 mils Carboline 3912 B
3 mils Carbozine 11+-
5 mils Phenoline 305 C
125 mils Amercoat 110 AA 5 mils Amercoat 66
'D 10 mils Plasite h
-Thermal Heat l
Conductivity Capacity Density 3
2 Material Mil-BTU /hr OF-ft BTU /lb-F LB/ mil-ft2 LB/ft i
Carbozine 11~
11,000-18,000 0.1-0.2 0.024 288 p
Phenoline 305 1,000- 3,500 0.3-0.4 0.009 108 Carboline 3912 7,000-12,000 0.2-0.3 0.017 204 1
Amercoat-110 AA-1,000- 3,500 0.3-0.4 0.011 132 Amercoat'66 1,000 -3,500 0.3-0.4 0.011 132 L_
Plasite 1,000- 3,500 0.3-0.4 0.011 132 1
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- 3. ' STARTING TIME OF. CONTAINMENT COOLING SYSTEMS ne starting times for the Reactor Building Coolers (22 seconds).and the Reactor Buidling Sprays (56 seconds) assumes instantaneous full flow operation in this system.
No credit is taken for the time it takes for the. pumps to attain rated speeds or valves to reach the open position.
%ese starting times represent only the time it takes to. fill the system piping at full flow operation.
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CONTAINMENT INITIAL CONDITIONh..
The initial values for temperature, pressure and relative humidity which were transmitted in our July 9,1975 submittal were based on operating experience to date.
The range of values which will be per-mitted during plant operation are as follows:
A.
Pressure
- Based 'on Technical Specification 3.6 the allowable range for pressure in the reactor building is 5.5 inches Hg vacuum to.
3.0 psig.
B. - Temperature Based on operating experience to date the expected range of temperatures will be:
Minimum 74F, Basement; 120F, Dome Maximum 100F, Basement; 145F, Dome It-should be noted that temperatures in the Reactor Building are not covered by Technical Specifications.
C.
Relative !!umidity Based on the temperatures presented in (B) above, the corres-ponding expected values for relative humidity is as follows:
At minimum temperatures, 45%, basement; 15% Dome At maximum temperatures, 20%, basement; 8% Dome It should be noted that relative humidity in the Reactor Building i
is not covered by Technical Specifications.
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5.
CONTAINMENT SPRAY WATER TEMPERA'11JRE Technical Specification 3.3.1(11) requires that the BWST water temperature be not less than 40F, Re temperature is maintained at or above 50F during plant operation, therefore ensuring that the ANO-1 spray water -
temperature is of a more conservative value than that presented in BAW-
, 10103.
He Reactor Building Spray System is designed for a flow rate of 1500 gpm.
Re value of 1800 gpm presented 'in BAW-10103 represents a maximum flow at zero head.
Piping restrictions for ANO-1 guarantee that a flow rate of less than 1800 gpm is obtained, and have been analyzed to show that the expected l-flow rate at the spray nos:les is 1500 gpm.
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6.
FAN-COOLER llEAT REMOVAL RATE The maximum. fan cooler heat removal rate is calculated to be approximately
'74 x 106 BTU /hr based on a reactor building atmosphere temperature of 286F and service water temperature of 40F, assuming all four (4) coolers are operatingI From BAW-10103, the maximum fan cooler heat removal rate is 57.55 x 10 BTU /hr based on the same temperatures as assumed above, llowever, the BAW-10103 calculation assumes only three (3) coolers in operacion.
The value of 286F in the reactor building is the same value as was used in the Final Safety Analysis Report for analysis of fan cooler perform-ance during emergency conditions.
The value of 40F for service water temperature is considered to be a conservative value.
If at any time the temperature were to be below this, the increase in fan cooler heat removal rate would not result in a rate in excess of that presented in BAW-10103.
The temperature rise across the pumps and piping (due to friction) will put the value within the 40F range. As operation of the coolers continues, tt.e service water temperature will rise as the water is being returned to the emergency cooling pond for recirculation through the plant systems. The rise #u temperature of the cooling pond is inevitabic, thereby ensuring that a continuous temperature of less than 40F is less than realistic and is not worthy of serious consideration as a true condition.
s From the calculated value for ANO-1 and the BAW-10103 value, it can be seen that the ANO-1 value is more conservative, i.e., the heat removal rate is approximately eight (8) times less that the value used in the generic analysis presented in this Topical Report.
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7.
Several parameters for Arkansas Nuclear One-Unit 1 are individually less conservative than those pre.ented in BAW-10103.
However, taken collectively and in combination with other parameters, ANO-1 is more conservative in the as-built condition than the BAW-10103 generic model.
The overwhelming consideration that must be taken into account is the nearly 400,000 cubic feet less net free volume in the reactor building when comparing ANO-1 to the generic model'. This smaller free volume in conjunction with less heat sink capacity than the generic model ensures that the reactor building pressure response for ANO-1 is more conservative than the model presented in BAW-10103.
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