ML17258A704
| ML17258A704 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/15/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TASK-04-02, TASK-4-2, TASK-RR LSO5-80-12-023, LSO5-80-12-23, NUDOCS 8101140070 | |
| Download: ML17258A704 (7) | |
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DEC ~ 8
><SO Dock et No. 50-244
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Nr. Leon D. Mhite, J r.
Vice President Electri c and Steam Production Rochester Gas 5
E 1ectri c Corporation 89 East Avenue Rochester New York 14649
Dear Nr. i<hite:
RE:
R.
E ~ GINNA - SEP TOPIC IV-2, REACTIVITY CONTROL SYSTENS DESIGN AND PROTECTION AGAINST SINGLE FAILURES The enclosed request for information has been prepared by the staff as a
part of our revi ew of SEP Topic IV-2.
Please provide the requested information within 30 days of receipt of this 1etter.
Sincerely,
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Enclosure:
Request for Information on SEP Topic IV-2 cc w/e ncl osure:
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Docket No. 50-244 LS05-80-1 2-023 1
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DEc 15 1M5 Mr. Leon D. White, Jr.
Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Mr" White:
RE:
R. E. GINNA -
SEP TOPIC IV-2, REACTIVITY CONTROL SYSTEMS DESIGN AND PROTECTION AGAINST SINGI E 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 30 days of receipt of this letter.
Sincerely,
Enclosure:
Request for Information on SEP Topic IV-2 cc w/enclosure:
See next page Dennis M. Crutchfield, ief Operating Reactors Branch 45 Division of Licensing
Mr. Leon D. White, Jr.
R.
E.
GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 CC Harry H. Voigt, Esquire
- Le8oeuf, Lamb, Leiby and MacRae 1333 New Hampshire Avenue, N.
W.
Suite 1100 Washington, D.
C.
20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Rochester Committee for Sci entific Informat i on Robert E. Lee, Ph.D.
P. 0. Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office-Swan Street Building Core 1,
Second Floor Empire State Plaza
- Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza Alba',
New York 12223 Rochester Public Library 115 South Avenue Rochester, New. York 14604 I
Supervisor of the Town of Ontari o 107 Ridge Road West
- Ontario, New York 14519 Resident Inspector R. E. Ginna Plant
.c/o U. S.
NRC 1503 Lake Road
- Ontario, New York 14519 Director, Technical Assessment Division Office of Radiation Programs
{AW-459)
U. S. Environmental Protection Agency Crystal Mall 4'2 Arlington, Virginia 20460 U. S. Environmental Protection Agency Region II Office ATTN:
EIS COORD INATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Dr. Richard F. Cole Atomic Saf ety and Licensing Board U. S. Nuclear Regulatory Comission Washington, D. C.
20555 Dr.
Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Mr. Thomas B. Cochran Natural Resources Defense Council, Inc.
1725 I Street, N.
W.
Suite 600 Washington,.D.
C.
20006 Ezra I. Bialik Assi s tant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047
ENCLOSURE RE(UEST 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.
I; 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 event of any of the single failures identified in Item I above.
4.
Identify the operating procedures, alarms, interlocks, or protection I
system actions which must be used in limiting the consequences following a single failure within systems used for reactivity control.
Where equipment actions are required, indicate whether the equipment meets tlie','
criteria of IEEE-279.