ML20039D345
| ML20039D345 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/30/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-15-12, TASK-RR LSO5-81-12-100, NUDOCS 8201040003 | |
| Download: ML20039D345 (3) | |
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December 30, 1981 Docket No.50-029 LS05 12-100 t A, t, a/ /
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1671 Worcester Road Framingham, Massachusetts 01701
Dear Mr. Kay:
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YANKEE R0WE - SEP TOPIC XV-12, SPECTRUM OF ROD EJECTION ACCIDENTS, REQUEST FOR ADDITIONAL INFORMATION We have reviewed the topic assessment on the above topic that you submitted on June 30, 1981, and we find that additional infonnation is needed to complete our safety evaluation.
Please provide the requested information w's in 30 days of receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, ONB clearance is not required under P.L.96-511."
Sincerely, Dennis H. Crutchfield, Chief Operating Reactors Branch No. 5 $bg S
Division of Licensing j
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, s Mr. James A. Kay cc Mr. James E. Tribble, President Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581 Greenfield Community College 1 College Drive
' Greenfield, Massachusetts 01301 Chairman Board of Selectnen 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 Resident Inspector Yankee Rowe Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350
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SYSTEMATIC EVALUATION PROGRAM TOPIC XV-12 YANKEE R0WE REQUEST FOR ADDITIONAL INFORMATION TOPIC: XV-12, SPECTRUM 0F R0D EJECTION ACCIDENTS The radiological consequences of the rod ejection event for Yankee Rowe were evaluated under the assumption of less than 10% fuel failure.
In your evaluation of this event, you predicted no fuel pin damage on the basis that the radially-averaged fuel enthalpy was less than 200 calories / gram. The staff does not accept the 200 cal /gm as a limit for clad damage.
Standard Review Plan 15.4.8 requires that the fission product inventory in the fuel rods calculated to experience a departure from nucleate boiling (DNB) condition be an input to the radiological evaluation.
Please provide justification that the fuel pin damage resulting from a rod ejection event would be less th n the
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