ML19340E334
| ML19340E334 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/15/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-04-02, TASK-4-2, TASK-RR LSO5-80-12-025, LSO5-80-12-25, NUDOCS 8101140068 | |
| Download: ML19340E334 (4) | |
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g DEC 15120 Docket No. 50-29 LS05-80-12-025 Mr. James A. Kay Senior Engineer - Licensing Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581
Dear Mr. Kay:
RE: YANKEE-ROWE - SEP TOPIC IV-2, REACTIVITY CONTROL SYSTEMS DESIGN AND PROTECTION AGAINST SINGLE FAILURES The enclosed request for information has been prepared by the staff as a part of our review of SEP Topic IV-2.
Please provide the requested information within 90 days of receipt of this letter.
Sincerely, y/
Dennis M. Crutchfield, ef Operating Reactors Branch #5 Division of Licensing l
Enclosure:
Request for Information on SEP Topic IV-2 cc w/ enclosure:
See next page t
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fl Mr. James A. Kay YANKEE-ROWE ATOMIC POWER STATION DOCKET NO. 50-29 cc Mr. James E. Tribble, President t
Yankee Atomic Electric Comany 25 Research Drive Westborough, Massachusetts 01581 i l l
Greenfield Cocrunity College j
1 College Drive Greenfield, Massachusetts 01301 Chairman Board of Selectmen l
Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council 14th Floor One Ashburton Place Boston, Massachusetts 02108
-Director, Techrdcal Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460 U. S. Environmental Protection Agency Region I Office ATTN: EIS C0ORDINATOR 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 m
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ENCLOSURE
.tEQUEST FOR INFORMATION SEP TOPIC IV-2 General Design Criterion 25 requires that the reactor protection system be designed to assure that specified acceptable fuel damage limits are not exceeded in the event of any single failure of the reactivity control systems, such as accidential rod withdrawals.
1.
Describe the single failures within systems used for reactivity control which can:
a) Cause an inadvertent reactivity insertion.
b) Cause a single or combination of rods to be positioned in other than the design sequence.
For PWRs this should include consideration of single rod withdrawal / insertions which can result from a single equipment component failure.
2.
Delineate those design features which limit reactivity insertion rates and rod malpositions resulting from a single failure. Provide the appropriate circuit schematics showing these design features.
3.
Provide or reference appropriate analyses to demonstrate that specified acceptable fuel damage limits are not exceeded in the evt.nt of any of l
the single failures identified in Item I sbove.
4.
Identify the operating procedures, alarms, interlocks, or protection system actions which must be used in limiting the consequences following l
a single failure within systems used for reactivity control. Where equipment actions are required, indicate whether the equipment meets tfje' criteria of IEEE-279.
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