ML20002C980
| ML20002C980 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/27/1969 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Walke G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML20002C981 | List: |
| References | |
| NUDOCS 8101150524 | |
| Download: ML20002C980 (6) | |
Text
DIRIBUTION:
I, W...Only, DR R. Engelken, CO (2)
H. K. Shapar, OGC N. Dube, DRL (5)
J. R. Buchanan, ORNL FEB 2: 1359 HQ PDR Docket File DRL Reading DR Reading Docket No. 50-155 Branch Reading W. D. Gilbert Consumers Power Company ACRS (3) 212 West Michigan Avenue D. J. Skovholt 1
Jackson, Michigan 49201 D. L. Ziemann J. J. Shea W. B. McKenna Attention: Mr. Gerald J. Walka R.DgEgeNo.16 Supervisory Engineer License No. DPR-6 Gentleasa Your Proposed Change No. 16 to the Technical Specifications of Operating License No. DPR-6, transmitted by letter dated January 22, 1969, and supplemented by telegram dated February 10, 1969, requeste that the Technical Specifications be changed to permit refueling of the Big Rock Point Nuclear Asactor core using modified Reload "E" type fuel which you have designated as asload "E-G" fuel.
We have reviewed the proposed change and have found that it does not present significant hasards considerations not described or implicit in the safety analysis report and that there is reasonable assurance that the health and safety of the public will not be endangered by authorising the use of Reload "E-G" fuel bundles in the Big Rock Point Nuclear Reactor. A copy of our related Safety Evaluation is enclosed.
Accordingly, pursuant to Section 50.59 of 10 CPR Part 50, the Technical Specifications of Operating License No. DPR-6 are hereby changed as set forth in Attachment A to this letter.
Sincerely, Pater A. Morris, 'ritactor Division of Reactor Licensing Enclosures 1.
Attachment A - Changes to Technical Specifications
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Safety Ivaluation I
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ATOMIC ENERGY COMMISSION W ASHINGTON, D.C. 20545 45 February 27, 1969 Docket No. 50-155 Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Attention:
Mr. Gerald J. Walke Change No. 16 Supervisory Engineer License No. DPR-6 Gentlemen:
Your Proposed Change No.16 to the Technical Specifications of Operating License No. DPR-6, transmitted by letter dated January 22, 1969, and supplemented by telegram dated February 10, 1969, requests that the Technical Specifications be changed to permit refueling of the Big Rock Point Nuclear Reactor core using modified Reload "E" type fuel which you have designated as Reload "E-G" fuel.
We have reviewed the proposed change and have found that it does not present significant hazards considerations not described or implicit in the safety analysis report and that there is reasonable assurance that the health and safety of the public will not be endangered by authorizing the use of Reload "E-G" fuel bundles in the Big Rock Point Nuclear Reactor. A copy of our related Safety Evaluation is enclosed.
Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, the Technical Specifications of Operating License No. DPR-6 are hereby changed as set forth in Attachment A to this letter.
Sincerely, n /. /,/ /' )
w.. (,.,
Peter A. Morris, Director Division of Reactor Licensing
Enclosures:
1.
- Attachment A - Changes to Technical Specifications i
2.
Safety Evaluation l
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t ATTACKHENT A CHANGE NO. 16 TO TECHNICAL SPECIFICATIONS OPERATING LICENSE NO. DPR-6 CONSUMERS POWER COMPANY DOCKET No. 50-155 1.
In line 1 of Section 5.1.5(c) Fuel Bundles, change the word "six" to read "seven".
2.
In Section 5.1.5.c, replace the present table titled " Fuel Bundles" with the attached revised table.
At the end of Section 5,. replace the present Figure 5.7 with the 3.
attached revised Figure 5.7.
4.
Under Section 5.2.1(b), change the column. titled " Reload 'E' Fuel" to read " Reload 'E' and 'E-G' Fuel".
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FUEL BUNDI.ES 515 ( Centd',
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Original Reload Reload Reload Centemelt Centermelt General (A)
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E-G "D" Fuel Intermediate Advanced Geometry, Fuel Rod Array 12 x 12 11 x 11 9x9 9x9 11 x 11 8x8 7x7 Rod Pitch, Inches 0.533 0.577 0.707 0.707 0.580 0.807 0.921 Standard Fuel Rods Per Bundle 132 109 74 70 109 36 29 Special Fuel Rods Per Bundle 121 122 73 315 12 28" 20" Spacers Per Bundle 3
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Fuel Rod Cladding Material 304SS Zr-2 Zr-2 Zr-2 304SS, Zr-2 Zr-2 Zr-2 Inconel 600 and/or Incoloy 800 Standard Rod Tube Wall, In.
0.019 0.034 0.040 0.040 0.010 to 0.030 0.035 0.040 Inclusive Special Rod Tube Wall, In.
0.031 0.031 0.040 0.040 0.010 to 0.030 0.035 0.040 Inclusive Fuel Rods Standard Rod Diameter, In.
0.388 0.449 0.5625 0.5623 0.425 0.570 0.700 Special Rod Diameter, In.
0.350 0.344 0.5625 0.5625 0.320 0.570 0.700 UO; Stacked Density, Percent 94 + 1 94 + 1 Pellet 90-95 Pellet 94 Pellets 90-95, Inclusive 94 Pellet 94 Pellet Theoretical 85 Powdered 85 Powder 85 Powder Active Fuel Length, Inches Standard Rod 70 70 69:75 70 68 to 70, inclusive 66-67.3 65-66.3
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2 peload' B,C.E and E-G Fuel Bundles May Contain (in the corner regions of the bundle) Fot.. Zr-2 Tubes llaving Encapsulated Cobalt Targets Scaled Within.
3 Reload E and E-G Fuel Bundles Have A Special Central Fuel Rod to Which the Bundle Spacers are Fixed. In addition, two of the interior bundle fuel rods are removable.
" Special Rods llave Depleted Uranitsa.
5 In Addition to Special Rods for Reload E, Reload E-G lias Four Gadolinia Containing Rods.
6 with 3'. Dishing on Selected Rods.
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