ML20002E019
| ML20002E019 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/09/1971 |
| From: | James Shea US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Ziemann D US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20002E016 | List: |
| References | |
| NUDOCS 8101260117 | |
| Download: ML20002E019 (1) | |
Text
'
5
\\_/
o UNITEC a TATES ATOMIC ENERGY COMMISSION
_+)i*
i l
1 7,g
' WASHINGTON, D.C. 20545
,,~
5 FEE 9 1971
.f.
i File (Dock No. 5 155f m w THRU:
D. L. Zie nn, Chief, ORB #2, DRL SAFETY REVIEW - BIG ROCK POINT - INSTRUMENTED FUEL ROD (CONSUMERS POWER COMPANY)
By Proposed Change No. 23 dated December 18, 1970, Consumers Power Company requested authorization to install one fuel rod instrumented with thermocouples inside the cladding into a modified Reload-F fuel bundle for irradiation in the Big Rock Point core.
The purpose of the thermocouples is to measure clad temperature during reactor oper-ation in a representative fuel bundle to evaluate crud laydown rates and heat transfer phenomena. We have redesignated -he request Proposed Change No. 22.
The nuclear and thermal-hydraulic characteristics of the instrumented F bundle will be substantially the same as due standard Reload-F bundles except that the fuel temperature will be slig.htly higher due to reduced fuel diameter and increased clad thickness to accommodate thermocouple leads. The upper end of the fuel rod end plug will be changed to per-mit extension o ~ the thermocouple leads out of the fuel rod.
The increase in clad thickness to 0.060 inch is necessary so 0.020 inch axial grooves can be cut on the inner surface of the cladding for the thermocouple lead wires.
The leadout assembly is similar to the instrumented fuel assembly used in the Big Rock Point Reactor during the research and development phase and incorporates design features of the current General Electric in-core sensors.
The reactor penetration and instrument leadout assembly utilizing the same flange in the reactor vess I head as was used for an earlier instrumented fuel assembly is based on proven designs. We have concluded that the instrumented fuel rod in a modified Reload-F fuel bundle will not change the nuclear or thermal performance characteristics signifi-cantly, or compromise the primary reactor system integrity and that the change does not represent a significant change in the hazards considerations described or implicit in the safe z, analysis report.
t'-\\
L/;;u)L$
ames J.'
ea perating Reactor Branch #2 Division of Reactor Licensing cc:
D. J. Skovholt, DRL J. J. Shea, DRL R. H. Vollmer, DRL R. M. Diggs, DRL D. L. Ziemann, DRL Mary Jinks (2) f/0/?6D//7
.