ML20058D884
| ML20058D884 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/21/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| IEB-79-01B, IEB-79-1B, LSO5-82-07-055, LSO5-82-7-55, NUDOCS 8207270429 | |
| Download: ML20058D884 (4) | |
Text
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Distribution July 21, 1982 Docket NRC PDR Local PDR ORB Reading Docket No. 50-29 NSIC D. Crutchfield LS05-82-07-055 H. Smith Mr. James A. Kay R. Camso
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OE Sanier Engineer Licensint:
0 Yankee Atomic Electric C apany 1671 Worcester Road ACRS (10)
SDB Framingham, Massachusetts 01701
Dear Mr. Kay:
SUBJECT:
ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT The staff review of the subject issue is continuing for the Yankee Nuclear Power Station (Yankee). However, the staff has identified additional information that is necessary to complete its review regarding equipment located outside containment. You are therefore requested to submit the information listed in the enclosure to this letter within 30 days of your
^
receipt ~ of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents. Therefore, OMB clearance is not required under Public law 96-511 l
Sincerely, Original Signed By Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page
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- James A. Kay Jult 21, 1982 cc Mr. James E. Tribble, President Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council 14th Floor
. One Ashburton Place Boston, Massachusetts 02108 U. S. Environmental Protection Agency Region I Office ATTN:
Regional Radiation Representative JFK Federal Building Boston, Massachusetts 02203 Massachusetts Department of Public Utilities ATTN:
Chairman Leverett Saltonstall Building Government Center 100 Cambridge Street Boston, Massachusetts 02202 Resident Inspector l-Yankee Rowe Nuclear Power Station c/o U.S. NRC P. O. Box 28 Monroe Bridge, Massachusetts 01350 l
Ronald C.. Haynes, Regional' Administrator
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Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 4
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EMCLOSURE 1 PRESSURE AND TEMPERATURE PROFILES FOR OUTSIDE CONTAINMENT REQUEST FOR INFORMATION Provide the basis, assumptions and an analysis of a typical pipe break
- location (for example, steam tunnel for BWR's or auxiliary feedwater pump room for PWR's) that includes the following information:
- 1. ' With respect to the pipe to be broken, provide the following:
Type of fluid (' water or steam);
a.
b.
Temperature; c.
Pressure; d.
Source of the fluid; e.
Flow rate (or assumed flow rate);
f.
Pipe internal diameter; g.
Wetted perimeter of the break (feet);
l 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.
n.
If item 1.m above 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.
2.
With respect to the compartments being analyzed, provide the following:
a.
Number of compartment analyzed; and
t.:
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b.
For each compartment:
1.
initial temperature 11.
initial pressure iii.
initial humidity iv.
free air volume (cubic feet) v.
number of vents and vent areas (square feet) for each vent; and vi.
minimum pressure to initiate flow to the next compartment (psia).
6 3.
Provide all assumptions used, including but not limited to the:
a.
Orifice coefficient for the "end effects" for the discharged fluid; and b.
Fluid expansion factor.
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.