ML20128B028
| ML20128B028 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/03/1975 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9212030542 | |
| Download: ML20128B028 (1) | |
Text
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Harch 3, 1975 Victtir Stello, Jr., Assistant Director for R-actt+r Safety, DTR REQUIRD'EtRS FOR ROD DROP ACCIDE}U IN OPERATING PIANTS Your memorandum of August 12, 1974, recommended that rod sequence control systems (RSCS) be installed in the operating plants listed below:
DOCKET !M!BER_
PLA.T-V 50-219 Oyster Creek 50-220 Nino Mile Point Unit 1 Dresden Units 2 and 3 50-237/249 50-245 Hillstone Point Unit 1 5 -254/265 Quad Cities Units 1 and 2 0-263 Plonticello 50-271 Vemont Yankee 50-293 P112rin Unit 1 The Vernont Yankee plant is the only plant of those cited'above that currently has a requirenent to install-a RSCS. The other plants are required by the Technical Specifications to have the rod worth ninimizer operable until 10% power; however, should the rod worth minimizer fail
'after withdrawal of the first 12 control rods, the Technical Specifications pemit the continuation of the startup providing that a second licensed operator verifies that the operator at the console is following the rod In nddition, there are supplemental procedural control aids program.
such as the control rod pattern templates that are used at Oyster Creek should the RLil fail after the first 12 rods are withdrawn.
Also,-in the case of Oyster Creek, recent proposed Technical Specification changes pemit one startup per calendar year should the RMI be inoperabic before a startup provided that a second licensed operator is present-and that the control rod pattern te:: plates are used, k'c believe that the existing Technical Specifications for control rod withdrawal-(and those currently proposed for Oyster Creek) are.ndequato to provido protection against an unlikely control rod drop accident. -
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We also believo that your recomendation to install RSCS in the above j
plants (except Vemont Yanlee) is a backfit requirement'. Therefore, we recomend that you bring this matter before the Regulatory Requirements i
R icw Comittee for a determination of NRC action.
f D STRIBUTION:-
ockets (10) Paulson OI6E (3)-
ORB #3 Rdg DeBevec Karl R. Goller, Assistant Director KRGoller DZiemann for Operating Reactors
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