ML20042C065
| ML20042C065 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/25/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-15-16, TASK-RR LSO5-82-03-099, LSO5-82-3-99, NUDOCS 8203300130 | |
| Download: ML20042C065 (3) | |
Text
DESIGNATED ORICINAL
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March 25,1982 Docket No. 50-29 LS05 03-099 P
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Y' Mr. James A. Kay
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'b Senior Engineer - Licensing
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, 3 '," C Yankee Atomic Electric Company
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i]D Framingham, Massachusetts 01701
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Dear Mr. Kay:
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SUBJECT:
YANKEE NUCLEAR POWER STATION - SEP TOPIC XV-16[ FAILURE OF SMALL LINES CARRYING PRIMARY COOLANT OUTSIDE CONTAINMENT -
REQUEST FOR ADDITIONAL INFORMATION In order to complete our review of SEP Topic XV-16, additional information is required.
Please provide answers to the enclosed questions within 30 days of receipt of this request.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, f %3RecST It:A.:
l Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
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Enclosure:
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Docket No. 50-29 Mr. James A. Kay cc Mr. James E. Tribble, President Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581 Greenfield Connunity College 1 College Drive Greenfield, Massachusetts 01301 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 l
Energy Facilities Siting Council 14th Floor One Ashburton Place i
Boston, Massachusetts 02108 U. S. Environmental Protection Agency Region I Office ATTN: EIS C0ORDINATOR JFK Federal Building l
Boston, Massachusetts 02203
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i Resident Inspector Yankee Rowe Nuclear Power Station c/o U.S. NRC l
j Post Office Box 28 Monroe Bridge, Massachusetts 01350 i
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,o INFORMATION REQUESTED FROM YANKEE ATOMIC FOR SEP REVIEW 0F YANKEE
, TOPIC.XV-16 Yankee jr evaluation states, "... operators would be signaled as soon as the leakage exceeded the makeup capability of a single charging pump."
State what the signal would be, how the operators would identify the line, and how the line would be isolated.
Specify the location of the isolation valves. Discuss the basis for the flow rate assumed, as compared to the flow rate that would be calculated by the method recommended in Standard Review Plan 15.6.2:
" amount of primary coolant released is conservatively l
estimated by assuming critical flow at the small line break location with the reactor coolant fluid enthalpy corresponding to normal reactor operating conditions."
Give the inner diameter and length (from reactor to outside of containment) of the instrument line for which the break was evaluated, and the basis for the 10 gpm leak assumed.
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