ML19345A424
| ML19345A424 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/06/1963 |
| From: | Bryan R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19345A422 | List: |
| References | |
| NUDOCS 8011210376 | |
| Download: ML19345A424 (1) | |
Text
.
..z
>p i
UNITED STATES ATOMIC ENERGY COMMISSION liAZARDS ANALYSIS BY THE RESEARCH AND POWER REACTOR SAFETY BRANCil DIVISION OF LICENSING AND REGULATION IN THE MATTER OF YANKEE ATOMIC ELECTRIC COMPANY
_.gr PROPOSED OIANGE NO. 33 DOCKET NO. S0-29 Introduction Pursuant to the provisions of Section 50.59 of the Commission's regulations, Yankee Atomic Electric Company in Proposed Change No. 33, dated March 19,
~.
1963, requested atuhorization of a change in the Technical Specifications
.f which are incorporated as a part of their operating license. The Proposed gf.;
Change would revise Precaution No. A.8. of NORMAL PLANT OPERATING INSTRUCTION HT NO. 504N to allow the Reactor Servo Control System to be adjusted so that it E:Es is capable of decreasing core reactivity by automatic rod insertion throughout
~~
the entire range of travel of the controlling rod group.
p 13==
Discussion IEN m
Amendment No. 41 to Yankee's operating license, which authorized increasing the reactor power level to 540 W thermal, required elimination of the si=
automatic withdrawal feature of the control rod system.
The automatic insertion capability of the system was retained, however.
Precaution No. A. 8; of NORMAL PLANT OPERATING INSTRUCTION NO. SO4N presently requires that the
~~
reactor must be operated in manual control when the controlling rod group is within 12 inches of travel limits.
Yankee believes, and we concur, that j
provision of the capability for automatic insertion of the controlling rod group into the reactor when the group is also near its limits of travel b_.
would be in the interest of improving the safety of operation.
Use of this I'-
feature would result in the immediate insertion of a rod group in the event of a sudden increase in the average temperature of the main coolant system water no matter what the position of the controlling rod group.
y ;;;;
Conclusion
[ --- -
We have concluded that the Proposed Change does not present significant hazards considerations not described or implicit in the hazards summary
.,. =
report, and that there is reasonable assurance that the health and safety of the public will not be endangered, m-Origir.al sbed
==
ty R: tut 11. Erfu
=14 Robert H. Bryan, Chief Research 6 Power Reactor Safety Branch
~~
Date:
Division of Licensing and Regulation
[
.