ML20002E027
| ML20002E027 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/22/1971 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Walke G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML20002E028 | List: |
| References | |
| NUDOCS 8101260138 | |
| Download: ML20002E027 (3) | |
Text
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February 22, 1971 Docket No. 50-155 Consumers Power Company 1 ATTN:
Mr. Gerald J. Walke c-Nuclear Fuel Management Administrator 212 West Michigan Avenue Jackson, Michigan 49201 Change No. 23 Gentlemen:
License No. DPR-6 Your Proposed Change No. 25 dated January 18, 1971, and TWX supplements thereto dated February 1 and 9 requested changes to the Technical Specifi-cations of Facility License No. DPR-6 to permit operation of the Big Rock Point Nuclear Reactor with two auxiliary antimony-beryllium neutron sources inserted in the reactor core. The auxiliary neutron sources would be con-tained in iemovable fuel rod positions in two fuel bundles to increase the starte count rate. We have redesignated your request Proposed Change No. 23.
We agree that the design of the auxiliary neutron sources is conservative and that safety may be enhanced by the insertion of and operatien with the proposed two sources because of the greater ability to measure neutron count rates. We have concluded that the proposed change does not increase the probability of or change the consequences of the design basis accident nor does it involve significant hazards considerations not described or implicit in the Safety Analysis Report. There is reasonable assurance that the health and safety of the public will not be endangered by oper-ation of the Big Rock Point Nuclear Reactor with two auxiliary antimony-beryllium neutron sources in the reactor core in the manner proposed.
Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, Section 5.1.6 of the Technical Specifications of Facility License No. DPR-6 is hereby changed to read as follows:
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... February 22, 1971 C nsumers Power Company _
"Section 5.1.6 Sources Type Antimony Beryllium Quantity
.2 Initial Sources and'up to 2 Auxiliary Sources Location
- The initial neutron sources shall be placed in Core Positions 02-59 and 09-52 as shown in Figure 5.1.
The two auxiliary neutron sources may each be con-tained in a removable rod in a fuel bundle located one fuel bundle position from the outside of the core, symmetrically near the E-W line through the center of the reactor core.
Physical Description The initial neutron sources shall consist-of a steel jacketed antimony pin,1 inch diameter by 12 inches long, centrally located on the vertical axis of a steel jacketed (Type 304 SS) beryllium cylinder 5-1/2 OD by 16 inches long. The entire assembly, including support structure, is a cylinder 79-7/16 inches long by 6 inches diameter which rests on a special orifice in a standard support tube and fuel channel. A lif ting bail shall be provided for handling purposes. The assembly design shall allow adequate cooling along the surface of the source pin and the outer surface of the assembly.
The auxiliary neutron sources shall each consist of a homogeneous 50-50 mixture of antimony-beryllium i
first encapsulated in a steel tube (Type 304 SS),
- With in-vessel low-level neutron detectors in service, one operating source may be temporarily relocated as the operator deems appropriate.
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.'then seco'ndarily encapsulated in a zirconium alloy. tube. :Each doubly encapsulated source will be equipped with a spring-loaded,: bayonet i
- latch locking device to permit it to be locked-into a-corner fuel rod position in a fuel bundle."
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Sincerely, i
Peter A. Morris Director Division of Reactor Licensing.
cc: George. F. Trowbridge, Esquire Shaw, Pittman, Potts, Trowbridge & Madden
- 910.- 17th Street,'N.W.
Washington,-D.C.
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Docket No. 50-155
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i Consumers Power Company ATTin Mr. Gerald J. Walke Nuclear Fuel Management Administrator 212 West Michigan Avenue Jackson, Michigan 49201 Change No. 23 License No. DPR-C Gentlemen.
Your Proposed Change No. 25 dated January 18, 1971, and 'lV.( supplements thereto dated February 1 and 9 requented changes to the Technical Specifi-cations of Facility License No. DPR-6 to permit operation of the Big Rock Point Nuclear Reactor with two auxiliary antimony-beryllium neutron sources inserted in the reactor core. The auxiliary neutron sources would be con-tained in removable fuel rod positions in two fuel bundles to increase the startup count rate. We have vedesignated feufvreques't' Proposed Change No. 23.
We agree that the design of the auxiliary neutron sources is conservative and enat safety may be enhanced by the insertion of and operation with the proposed two sources because of the greater ability to measure neutron count rates. We have concluded that the proposed change does not increase the probability of or change the consequences of the design basis accident nor does it involve significant hazards considerations not described or implicit in the Safety Analysis Report. There is reasonable assurance that the health and safety of the public will not be endangered by oper-ation of the Big Rock Point Nuclear Reactor with two auxiliary antimony-beryllium neutron sources in the reactor core in the manner proposed.
Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, Section 5.1.6 of tne Technical Specifications of Facili'y License No. WR-6 is hereby changed to read as follows:
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Consu'ners Power Company 2 bil "Section 5.1.6 Sources Type Antimony Beryllium Quantity 2 Initial Sources and up to 2 Auxiliary Sources Location
- The initial neutron sources shall be placed in Core Positions 02-59 and 09-52 as shown in Figure 5.1.
The two auxiliary neutron sources may each be con-tained in a removable rod in a fuc1 bundle located one fuel bundle position from the outside of the core, symmetrically near the E-W line through the center of the reactor core.
Physical Description The initial neutron sources shall consist of a stec1 Jacketed antimony pin,1 inch diameter by 12 inches long, centrally located on the vertical axis of a steel jacketed (Type 304 SS) beryllium cylinder 5-1/2 OD by 16 inches long. The entire assembly, including support structure, is a cylinder 79-7/16 inches long by 6 inches diameter which rests on a special orifice in a standard support g.
tube and fuel channel. A lifting bail shall be provided for bandling purposes. The assembly v.
4 design shall allow adequate cooling along the surface of the source pin and the outer surface of the assembly.
The auxiliary neutron sources shall each consist of a homogeneous 50-50 mixture of antimony-beryllium first encapsulated in a steel tube (Type 304 SS),
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- With in-vessel low-level neutron detectors in service, one operating source may be temporarily relocated as the operator deems appropriate.
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Consumers Power Company FEB 5 21971 then secondarily encapsulated in a zirconium alloy tube. Each doubly encapsulated source will be equipped with a spring-loaded, bayonet latch locking device to permit it to be locked into a corner fuel rod position in a fuel bundle."
Sincerely,
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Peter A. Morris, Director Division of Reactor Licensing cc: George F. Trowbridge, Esquire Shaw, Pittman, Potts, Trowbridge & Madden 910 --17th Street, N.W.
Washington, D.C.
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