ML20055C060
| ML20055C060 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/05/1982 |
| From: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| IEB-80-04, IEB-80-4, TAC-46851, TAC-46852, NUDOCS 8208100084 | |
| Download: ML20055C060 (5) | |
Text
c WISCONSIN Electnc eowca couraur 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE. WI 53201 August 5, 1982 Mr. H.
R.
Denton, Director Office of Nuclear Reactor Regulation U.
S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention:
Mr.
R.
A. Clark, Chief Operating Reactors Branch 3 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 ADDITIONAL INFORMATION REGARDING HIGH ENERGY LINE BREAKS OUTSIDE CONTAINMENT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In a letter to us dated July 1, 1982, Mr.
R. A.
Clark of your staff requested additional information regarding the generation of temperature / pressure profiles for typical high energy line breaks (HELB) outside containment at Point Beach Nuclear Plant, Units 1 and 2.
In a telephone conversation with Mr.
R.
K. Hanneman of our staff on July 7, 1982, Mr. T. G. Colburn, the NRC Project Manager for Point Beach, stated that information for one typical postulated HELB outside containment would be sufficient and that the information would be used to verify the environmental service conditions used for the environmental quali-fication of safety-related electrical equipment outside containment at Point Beach.
I Enclosures 1 and 2 provide the requested information for a postulated break of a 30-inch main steam line in the turbine building at Point Beach.
The analysis upon which this information is based was performed by Bechtel Power Corporation in 1973.
The steam generator blowdown mass flowrate and enthalpy as a function of time were provided by Westinghouse Electric Corporation.
We would be pleased to answer any questions you may have regarding this information.
Verv truly yours, m
V h,dr i
~
ec ice President
)() [
Sol Burstein Enclosures Copy to NRC Resident Inspector 8208100084 820805 PDR ADOCK 05000266 P
ADDITIONAL INFORMATION CONCERNING HIGH ENERGY LINE BREAK ANALYSIS OUTSIDE CONTAINMENT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Case:
Pipe break of the 30-inch main steam line in turbine building (T/B) near the cable spreading room door.
1.
With respect to the pipe to be broken:
a.
Type of fluid (water or steam) :
steam b.
Temperature:
547*F c.
Pressure:
1,020 psia d.
Source of the fluid:
Flow rate (or assumed flow rate) :
see blowdown data in Enclosure 2.
f.
Pipe internal diameter:
28.184 inches g.
Wetted perimeter of the break (feet) :
7.38 feet h.
-Total pipe internal volume:
not considered i.
Exit flow area, if the break was not in the pipe just described above:
N/A j.
Area of flow restriction, if any:
not considered k.
Differential elevation from the source to the pipe break:
65 feet 1.
Total flow resistance (only if the fluid is water) :
N/A m.
Means to stop fluid flow (none, gate valve, globe valve, etc. ) :
If i.m is a valve, then the valve's open throat area, full open flow coefficient, valve closure time, and delay time until initiation of valve closure:
valve closure time is six seconds, closure initiation delay time is 2.45 seconds, and piping blowdown time is 1.55 seconds.
The other information was not used.
Page 1 of 3
B 2.
With' respect to the compartments being analyzed:
a.
Number of compartments analyzed:
3 i.
T/B @ El.
8' ii.
T/B @ El. 26' iii.
T/B @ El. 44' b.
For each compartment:
i.
Initial temperature:
not. considered ii.
Initial pressure:
O psig forJall compartments iii.
Initial humidity:
not considered iv.
Free air volume ' (cubic feet) :
3 (1) 390,000 ft 3
(2) 390,000 ft (3) 2,100,000 ft3 v.
Number of vents and vent areas (square feet) for each vent:
2 (1) one vent, (1) to (2), 4,700 ft to (1), 4,700 ft2, and (2) to (3),
(2) two ventg, (2) 4,625 ft (3) one vent, to atmosphere, 25,000 ft2@ >0.5 psig vi.
Minimum pressure to initiate flow to the next compartment (psia) :
(1) 14.7 psia (2) 14.7 psia (3) 15.2 psia 3.
Assumptions used:
a.
Orifice coefficient for the "end effects" for the discharged fluid:
not considered b.
Fluid expansion factor:
not considered Page 2 of 3
a c.
Assumed plant at hot standby since this operating mode yields the highest operating steam conditions.
d.
Full area circumferential break (guillotine) of the 30-inch main steam line at the turbine bypass tee to develop the pressure response curves for the turbine building.
e.
Assumed six seconds for valve closure time and valve closes on signal starting at 2.45 seconds after initiation of break.
f.
Assumed total pressure at a component equals the sum of the compartment pressure plus the jet impingement forces, if any.
g.
Assumed temperature equals the maximum temperature of superheated steam at the compartment pressure with a constant enthalpy expansion process.
1 l
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a
-,.,.--.i-s_
y, c,
,--.-,.y-
TABLE 1.
ESTIMATED MASS AND ENERGY RELEASE RATES FOR 30-INCH MAIN STEAM LINE DOUBLE-ENDED RUPTURE
- POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Time (rec)
Mass Flow (lbm/sec)
Enthalpy (Btu /lbm) 0-
.43 18,200 1190
.43 - 1.0 2,964 1190 1.0 - 10.0 10,300 570
> 10.0 0
0 4
4
- Estimate obtained from T.
Burnett and J. Kendall of Westinghouse Electric Corporation by telecon with K.
E.
Schwartztrauber of Bechtel on January 15, 1973.
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