ML20054M655
| ML20054M655 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/01/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Fay C WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 8207140119 | |
| Download: ML20054M655 (3) | |
Text
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JUL 1 1';gg
- O DJSTRIBUTION
v00cket File NRC PDR Docket Nos. 50-266 Local PDR and 50-301 ORB # 3 Rdg D. Eisenhut J. Heltemes, AE0D FMKreutzer-3 Mr. C. W. Fay RAClark Assistant Vice President T. Colburn Wisconsin Electric Power Company 0 ELD 231 West Michigan Street I&E Milwaukee, Wisconsin 53201 NSIC ACE-10
Dear Mr. Fay:
On June 22, 1982 we telecopied to Mr. H. Hanneman of your staff a request for additional infomation related to temperature / pressure profiles for typical high energy line pipe breaks (HELB) outside containment for Point Beach Units 1 and 2.
We have requested Mr. Hanneman to telecopy the infomation back to us as soon as possible. This letter constitutes our fomal re-quest for this infomation.
Please provide a written response to the questions contained in enclosure 1 within 30 days of receipt of this letter. As discussed with Fr.
Hanneman, this infomation is of a clarifying nature, to provide us with the parameters used in your previously perfomed analysis on HELB outside containment.
The reporting /and or t-ecordkeeping requirements contained in this letter affect fewer than ten respondents; therefore OMB clearance is not required under P.L.96-511.
Sincerely, Originalsigned by Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosures:
As stated cc: See next page 8207140119 820701 PDR ADOCK 05000266 P
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OFFiClAL RECORD COPY usceousn-m em nnc ronu m oo.ao3 nacu cao
J Wisconsin Electric Power Compary cc:
Mr. Bruce Churchill, Esquire Mr. William Guldemond Shaw, Pittman, Potts and Trowbridge USNRC Resident Inspectors Office 1800 M Street, N. W.
6612 Nuclear Road Washington, D. C.
20036 Two Rivers, Wisconsin 54241 Joseph Mann Library Peter B. Bloch, Chairman 1516 Sixteenth Street Administretive Jedge Two Rivers, Wisconsin 54241 Atomic Safety and Licensing Board' U.S. Nuclear Regulatory Commission Mr. Glenn A. Reed, Manager Washington, D. C.
20555 Nuclear Operations Wisconsin Electric Power Company Dr. Hugh C. Paxton Point Beach Nuclear Plant Administrative Judge 6610 Nuclear Road 1229-41st Street Two Rivers, Wisconsin 54241 Los Alamos; New Mexico 87544 Mr. Gordon Blaha Dr. Jerry R..Kline Town Chairman Administrative Judge Town of* Two
- Creeks Atomic Safety and Licensing Board Route 3 U.S. Nuclear Regulatory Commission Two Ri. vers, Wisconsin 54241 Washington, D. C.
20555 Ms. kathleen M. Falk Francis X. Davis General Counsel P. O. Box 355 Wisconsin's Environmental Decade Pittsburgh, PA 15230 114 W. Carroll Street Madison, Wisconsin 53703
- h. S. Environmental Protectio'n Agency Federal Activities Branch Region V Office ATTN: Regional Radiation Representative 230 S. Dearborn Street Chicago, Illinois 60604 Chai rman Public Service Commission of Wisconsin Hills Farms State Office Building Madison, Wisconsin 53702 Regional Administrator Nuclear Regulatory Commission, Region III Office of Executive Director for Operations 799 Roosevelt Road Glen Ellyn, Illinois 60137
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Requestlor__ Additional Information Concernig High Energy Line Break Analysis Outside Containment 1.
With respect to the pipe to be broken, we need to know the:
Type of fluid (water or steam);
a.
b.
Temperature; c.
Pressure; d.
Source of the fluid; Flow rate (or assumed flow rate);
e.
f.
Pipe internal diameter; g.
Wetted perimeter of the break (feet);
h.
Total pipe internal volume;
- i. Exit flow area, if the break was not in the pipe, just described above;
- j. Area of flow restriction, if any; k.
Differential elevation from the source to the pipe break; 1.
Total flow resistance (only if the fluid is water);
Means to stop fluid flow (none, gate valve, globe valve, etc.); and m.
If 1.m is a valve, then the valve's open throat area, full open flow n.
coefficient, valve closure time, and delay time until initiation of valve closure.
2.
With respect to the compartments being analyzed:
a.
Number of compartments analyzed; and b.
For each compartnent:
1.
initial temperature ii. initial pressure iii.
initial humidity iv.
free air volume (cubic feet) number of vents and vent areas (square feet) for each vent; and l
v.
vi. minimum pressure to initiate flow to the next compartment (psia).
I 3.
All assumptions used, including but not limited to the:
Orifice coefficient for the "end effects" for the discharged fluid; and a.
b.
Fluid expansion factor.
_