ML19345E412
| ML19345E412 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/14/1966 |
| From: | Doan R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Wall H CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML19345E413 | List: |
| References | |
| NUDOCS 8101160419 | |
| Download: ML19345E412 (5) | |
Text
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Distributiona Domer.t ?xo.1 p
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ATOMIC ENERGY COMMISSION Fo r".cl Supplen::ntal I
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- A WASHINGTON, D.C. 20545
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_ D2L Reading Originator: T,Grir m C. l!cnc'erc<n APR 141966
- c. c. cccc Docket No. 50-155 J. Shen li. Stecle li. Shnpar L.1;ornblith (2)
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Change No. 8 Consumers Power Company 1945 Parnell Road TIEar,f Jackson, Michigan 49201
- c. Paac D. Shovholt Attention:
Mr. H. R. Wall 1;. Jinks (4)
Vice President bec:
- h. J.1:cAlduff, 0?.0 E. Trennel, IP Gentlemen:
- n. Leith, OC The Consumers Power Company, by letters dated December 23,1965, March 15,1966 and supplement letter date ' March 17, 1966, has requested changes in the Tech-nical Specifications of se No. DP'-6, dated May 1,1964, for the Big Rock Point reactor. The r
,ud changes involve the use of zircaloy clad reload fuel in place of the tuinless steel clad fuel used in the original core and the inclusion of cobalt targets in the zircaloy-clad reload fuel bundles.
This request has been designated Proposed Change No. 8 and has been reviewed in accordance with the provisions of Section 50.59 of the Commission's regula-tions. We have found that the proposed change does not present significant hazards considerations not described or implicit in the hazards su= mary report and there is reasonable assurance that the health and safety of the public vill not be endangered. A copy of the related safety evaluation is enclosed.
Accordingly, pursuant to Section 50 59,10 CFR 50, the Technical Specifications of Operating License No. DPR-6 are changed as set forth in Attachment A to this letter.
Sincerely yours, OrigMat Siped By R.L Dosa R. L. Doan, Director Division of Reactor Licensing
Enclosures:
1.
Attachment A to Change No. 8 2.
AEC Safety Evaluation l
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APR 1 4 y99 ATTACHMH;T A CONSUMERS POWER -COIGANY 4 -
CHANGES TO TECHNICAL SPECIFICATIONS CHANGE NO. 8 (1) Delete the present section 515 and replace it with the following:
'"5.1.5 _ General Core Composition The crta in this section present general design features of the criginal fuel, research and development fuel and relcad fuel tnat shall make up the physical compositicn of the core.
(a) Enrichment of-Fuel, approximate weight percent U-235 from :
2.6 to 4 5, inclusive.
(b) General Core Data:
Number of Fuel Bundles in Core, A Maximen of 86 7
Total Nominal Weight UOg in 8h Bundles, Lb 29,300 Moderator-to-Fbel Volume Ratio 2.65 Equivalent Core Diameter (Approximate), Inches 77 (c) Fuel Bundles:
The general dimensions and configuration of the three types of fuel bundles shall be as shown in Figures 5 2, 5 3 and 8.1 of these specifications. Principal design features shall be essentially as follows:
Fuel Bundles General Original Reload Research & Development Geometry, Fuel Rod Array 12 X 12 11 X 11 11 X 11 Rod Pitch, Inches 0 533 0.577 0.580 Standard Fbel Rods per Bundle 132 109 109 S ecial Fuel Ecd per Bundle 12*
12**
12 ShacersperBundIe 3
5 7
- (h Special Fuel Bods at Bundle Corners Are Segmented)
(Reload fuel bundles 1may contain (in the corner regions of the bundle) four i
Zircaloy-2 tubes having encapsulated cobalt targets sealed within) 1 a
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2-Fuel Bundles Original Eeload.
Research & Development
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Fue1 Rod Cladding 4
Material.
- 304 SS Zr-2
- 304 SS, Zr-2
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Inconel 600 and/orIncolcy800 7
Standard Rod Tube Wall, ' Inches 0.019 0.034',
0.010 to 0.030, Inclusive-Special' Rod Tube Wall, Inches 0.031 0'.031.
0.030 to 0.030, Inclusive Fuel Rods 0 388 0.449
. 0.425
. Standard Rod Diameter, Inches Special Rod Diameter, Inches
' O.350
- 0 344 0 320 UO2 Density, Percent Theoretica19421 94 : 1 90 to 95, Inclusive
-Active Fuel. Length, Inches Standard 70-70 68 to 70, Inclusive Corner 59 4
Fill' Gas Helium
- Helium Helium (d) Channels
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Number 'of 304 SS and/or. Zr-2 88 I
Wall Thi:kness, Inches:
304 SS 0.075 Zr-2 0.100 l
Inside Width,-Inches:
304 SS 6.57 Zr-2 6.54 Length, Inches:
304 SS 79-5/8 Zr-2 79-3/4 (e) Total Weight Supported by Core Support Plate:
I
. 86 Fbel Bundles @ hh0 Lb/ Bundle, Lb 37,840 88 Support-Tube-and-Chennel ~ Assemblies
@100Lb/ Assembly,Lb 8,800 86 Orifices @ 10 Lb/ Orifice, Lb 860 2 Channel Plugs G 10 Lb/ Plug, Lb 20 1 Flow Distributor Assesbly, Lb 2,500 4
Tbtal Weight, Lb 50,020
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. (2) Add a New Section - 5.1.7:
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"5 1.7 Zr-cr Alloy Test Bundle One of the reload fuel bundles may contain up to 18 rods (2 dummy and 16 fuel rods) clad with an annealed Zril.15 w/o Cr alloy and up to 8 rods (2 dummy and 6 fuel rods) clad with annealed special Zr-2.
The remaining fuel rods in the bundle (maximum of 95) chall be clad with cold-worked standard Zr-2."
(3) Add a new seution 6.1.6:
"The automatic actuation of the containment spray shall occur within 5 minutes of the receipt of a high containment pressure signal if more than one-half the fuel bundles in the core are zirconium clad."
(4) Delete the present section 7.5,7 and replace it with the following:
"7.5.7 It shall be permissible to remove a centrol rod drive from the reactor vessel when the reactor is in the shutdown con-dition and the mode selector switch ic locked in the " Shutdown" position.
The core shutdown margin of 0.3% keff/keff with the strongest control rod out of the core shall have been met prior to the control rod drive removal; and in addition, the equipment shall be properly tagged.
The control rod drive that was removed shall without delay be replaced by a spare centrol rod drive or the original control rod drive shall be reinstalled.
One control rod drive pump shall be operating during removal and reinsertion nd during the time the control rod drive is out-side the reac or vessel."
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