ML20002E021
| ML20002E021 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/03/1971 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Walke G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML20002E022 | List: |
| References | |
| NUDOCS 8101260126 | |
| Download: ML20002E021 (7) | |
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4 UNITED STATES ATOMIC ENERGY COMMISSION
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WASHINGTON. D.C.
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March 3, 1971 s
Docket No. 50-155 Consumers Power Company ATIN:
Mr. Gerald J. Walke Nuclear Fuel Management Administrator 212 West Michigan Avenue Jackson, Michigan 49201 Change No. 24 Gentlemen:
License No. DPR-6 We have reviewed your Proposed Change No. 24 dated December 21, 1970, to the Technical Specifications of Facility License No. DPR-6 for reactor operation with two new centermelt fuel bund]'_a and five of the original six centermelt fuel bundles.
The new centermelt fuel bundles are different from the original center-melt assemblies in the following respects:
- 1) sheet metal corner angles have been eliminated, 2) removable cobalt targets have been placed in new stainless steel corner tubes, 3) there are fewer (16 compared with 29 and 36) high power fuel rods, and 4) rod-to-rod power gradients have been reduced. Before the five original centermelt fuel assemblies that were irradiated during April, May and June 1967 are returned to the Big Rock Point Nuclear Reactor, the crud accumulated during that irradiation period will be removed by chemical cleaning and eight of the high power rods in the outer rows vill be replaced by low power rods. With two new centermelt fuel bundles in the core, there will be a total of 32 high power rods at or near centermelt conditions at rated power. When the five original centermelt fuel assemblies have been reconstituted and reinserted into the Big Rock Point core, the total number of high power rods will be 172 compared with 188 for the six centermelt fuel bundles as originally fabricated and irradiated in the Big Rock Point core in March 1967.
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We have concluded that the proposed change does not present significant hazards considerations not described or implicit in Consumerd Safety Analysis Report and Proposed Change No. 13 dated May 26, 1967, and approved by DRL Amendment No.1 to the Facility Operating License No. DPR-6 dated March 12, 1968. There is reasonable assurance t';at the health and safety of the public will not be endangered by operation of the Big Rock Point Nuclear Recctor in the manner described by Consumers f<lolc%of9b fL
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Consumers Power Company March 3, 1971
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Power Company with two new centermelt fuel bundles or with the two new centermelt fuel bundles and five of the original centermelt fuel bundles as proposed.
Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, the Technical Specifications of Facility License No. DPR-6 are hereby changed as indicated in Attachment A to this letter.
Sincerely, 03 4 4. ka Peter.A. Horris, Director Division of Reactor Licensing
Enclosure:
Attachment A - Changes to Technical Specifications t
i cc: George F. Trowbridge, Esquire t
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ATTACHMENT A
_CRANGE NO. 24 TO TECHNICAL SPECIFICATIONS FACILITY LICENSE NO. DPR-6 CONSUMERS POWER COMPANY DOCKET NO. 50-155 1.
Change the first paragraph of Section 8.1 to read:
"8.1 The general dimensions and configuration of the developm Principal design features shall be essentially as s en tal Table 8.1."
n 2.
Section 8 - Figures:
Add Figure 8.6 - New Intermediate Performance Fuel Cent (8 x 8 Array) and Figure 8.7 - New Advanced Performanc ermelt Assembly Assembly (7 x 7 Array).
e Fuel Centermelt 3.
Delete Table 8.1 and insert the revised Table 8.1.
4.
Table 8.2 - Change the number of ce ntermelt fuel bundl es to read:
" Number of Buniles Centermelt Intermediate Advanced Pellet UO2 Powder UO2 3
1 1
2 5.
Change Section 8.2.l(c) to read:
"(c) Fuel Examinations Nondestructive examinations of selected fuel rods in th refueling period.centermelt fuel bundles shall be performed during each core e
in diameter shall not be returned to the core.Any rods displaying un Selected fuel rods shall be removed during each refueli period for destructive examinations.
ng The bundles shall be to the core for continued irradiation." reconstituted with replace
W Footnotes to Table 8.1-
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(1)hiodified E-G and EEI UO -Pu0 and new centermelt fuel bundles may contain (in the corner regions.of the bundle).
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four Zr-2 tubes having' encapsulated cobalt targets' sealed within.
(2) Modified E-G and EEI UO -Pu0 fuel bundles have a special central fuel rod to which the bundle spacers are 2
2
. fixed. -In addition, two of the interior bundle fuel rods are removable and may contain UO -Pu02 f"'I*
2 (3)Special rods have depleted uranium.
( }Also has four gadolinia-containing rods.
(5)With 3% dishing on selected rods.
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'(0}UO -Pu0 fuel rod stack density will vary from 74 to 92% theoretical by using annular, dished, or nondished 3
2 pellets in selected rods.
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rods, four cobalt corner rods and one empty (waker ds, four removable Pu0filledduringoperatiod) rods,eightgadolinia-co Sixty-four UO -PuO r ds similar to standard UO ro 2
spacer rod.
Diameter of cobalt targets inside SS corner tubes.
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FIGURE 8.6 NEW INTERMEDIATE PERFORMANCE FUEL CENTERMELT ASSEMBLY (8x8 ARRAY)
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i FIGURE 8.7 NEk' ADVANCED PERFORMANCE FUEL CENTERMELT ASSEMBLY (7x7 ARRAY)
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