ML20002C977
| ML20002C977 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/02/1968 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML20002C978 | List: |
| References | |
| NUDOCS 8101150518 | |
| Download: ML20002C977 (6) | |
Text
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DISTRIBUTION:
W. Dooly, DR R. Engelken, CO (2)
H. K. Shspar, OGC N. Dube, DRL (5) 1968 J. R. Buchanan, 001 Mg Document Room Bocket No. 50-155 SUPPL DRL Reading DR Reading Branch Reading
..CRS (3)
Consumers Power Company Formal j
212 West Michigan Avenue D. J. Skovholt Jackson, Michigan 49201 S. Levine J. Shea D. Ziemann R. Diggs Attention:
Mr. Robert Esmeter Assistant Electric Production Change No. 14 1
Superintendent License Eo. DPR-6 Gentlemen:
Proposed Change No.14 to the Tschaical Spacifications of License No.
DPR-6, submitted by your letter dated February 6, 1968, and modified by an Addendum dated May 10, 1968, and a telegram received June 17, 1968, request.s that the Technical Specifications be changed to per=it Esload "E" fuel, which incorporatas the Generst Electric Company's current comrnercial design featurw, to be inserted into the Big Rock Point reactor.
We have found that the proposed change, as modified, 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. Accordingly, pursuant to Section 50.59 of 10 CFR 50, the Technical Specifications are hereby changed as set forth in Attachment A to this letter.
A copy of our related safety evaluation is also enclosed.
Sincerely, Peter A. Morris, Director IIdd Division of Isactor Licensing 3
j Enclosurast
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Attachment'A - Change Es. 14 y'f
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Safety Evaluation
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July 2, 1968 F
Docket No. 50-155 Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Attention:
Mr. Robert Haueter Assistant Electric Production Change No. 14 Superintendent License No. DPR-6 Gentlemen:
Proposed Change No. 14 to the Technical Specifications of License No.
DPR-6, submitted by your letter dated February 6, 1968, and modified by an Addendum dated May 10, 1968, and a telegram received June 17, 1968, requests that the Technical Specifications be changed to permit Reload "E" fuel, which incorporates the General Electric Company's current commercial design features, to be inserted into the Big Rock Point reactor.
We have found that the proposed change, as modified, 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 scfety of the public will not be endangered. Accordingly, pursuant to Section 50.59 of 10 CFR 50, the Technical Specifications are hereby changed as set forth in Attachment A to this letter.
A copy of our related safety evaluation is also enclosed.
Sincerely, Peter A. Morris, Director Division of Reactor Licensing
Enclosures:
1.
Attachment A - Change No. 14 2.
Safety Evaluation 1
j
ATTACHMENT A DOCKET NO. 50-155 CONSUMERS POWER COMPANY CHANGES TO TECHNICAL SPECIFICATIONS CHA"7.) NO. 14 LICENSE NO DPR-6 1.
Delete the present section 5.1.5(c) and replace it with the following:
"5.1.5(c) Fuel Bundles The general dimensions and configuration of the six types of fuel bundles shall be as shown in Figures 5.2, 5.3, 5.4, 5.5, 5.6, 5.7 and 8.1 of these specifications.
Principal design features shall be essentially as follows:"
2.
Delete the present tab'.e of fuel parameters following section 5.1.5(c) and replace it with the attached.
3.
Add the attached Figure 5.7 to the fuel assembly figures following Section 5.
4.
Delete the present Section 5.2.1(b) and replace it with the following:
"(b) Reactor Operation The roactor operation shall be so limited as to be consistent with the most conservative of the following:
Original
("A"), "B "
Reload and "C" Fue_1 "E" Fuel.
- Minimum Core Burnout Ratio at Overpower 1.5 1.5 Transient Minimum Burnout Ratio in Event of Loss of Recirculation Pumps from Max mu Heat Flux at Overpower, BTU /Hr-Ft 530,000 5b0,000 2
2 Maximum Steady State Heat Flux, BTU /Hr-Ft 434,000 410,000 Maximum Fuel Rod Power at Overpower, Kw/Ft 17.2 21.6 l
Maximum Steady State Fuel Rod Power, Kw/Ft 14.2 17.7 l
i
t Original
("A"), "B" Reload and "C" Fuel "E" Fuel Stability Criterion: Maximum Measured Zero-to-Peak Flux Amplitude, Percent of Average Operating Flux 20 20 Maximum Steady State Power Level, Mwt 240 240 Maximum Value of Average Core Power Density @ 240 Mwt, Kw/L 46 46 Maximum Resctor Pressure During Power Operation, psig 1485 1485 Minimum Recirculation Flow Rate, Lb/Hr (Except During Pump Trip Tests or Natural Circulation Tests as Outlined 6
6 in Section 8) 6 x 10 6 x 10 Maximum Mwd /T of Contained Uranium for an Individual-Bundle 23,500 23,500 Rate of Change of keactor Power During Power Operation:
Control rod withdrawal during power operation shall be such that the average rate of change of reactor power is less than 50 Mwt per minute when power is less than 120 Mut, less than 20 Mwt per minute when power is between 120 and 200 Mut, and 10 Mwt per minute when power is between 200 and 240 Mwt.
- Based on correlation given in ' Design Basis for Critical Heat Flux Condition in Boiling Water Reactors', by J. M. Healzer, J. E. Hench, E. Janssen, and S. Levy, September 1966 (APED 5286 and APED 5286, Part 2)."
1
Fuel Bund 1m Research and Development Centermelt Centermelt General O_riginal (A)
Reload B & C Reload E "D" Fuel Intermediate.
Advanced _
Geometry, Fuel Rod Array 12 x 12 11 x 11 9x9 11 x 11 8x8 7x7 Rod Pitch, Inches 0.533 0.577 0.707 0.580 0.807 0.921 Str.ndard Fuel Rods per Bundle 132 109 74 109 36 29 Sprcial Fuel Rods per Bundle 12*
12**
7***
12 28#
20#
Sp:cers per Bundle 3
5 3
7 5
5 Fusi Rod Claddig haterial 304 SS Zr-2 Zr-2 304 SS, Zr-2 Zr-2 Zr-2 Inconel 600 and/or Incoloy 800 Sttndard Rod Tube Wall, In.
0.019 0.034 0.040 0.010 to 0.030, 0.035 0.040 Inclusive SpIcial Rod Tube Wall, In.
0.031 0.031 0.040 0.010 to 0.030, 0.035 0.040 Inclusive Futi Rods Sttndard Rod Diameter, In.
0.388 0.449 0.5625 0.425 0.570 0.700 Sptcial Rod Diameter, In.
0.350 0.344 0.5625 0.320 0.570 0.700 UO Density, Percent 94 1 1 94 1 1 Pellet 90 to 95, Inclusiva 94 Pellet 94 Pellet Theoretical 85 Powdered 90-95 Pellet 85 Powder 85 Powder 2
Active Fuel Length, Inches i
Standard Rod 70 70 69.75 68 to 70, Inclusive 66-67.3 65-66.3 64.6 (Cen-Special Rod 59 (Corner) tral)
Fill Gas Helium Helium Helium Helium Helium Helium Four Special Fuel Rods at Bundle Corners Are Segmented Reload B, C & E Fuel Bundles May Contain (in the Corner Regions of the Bundle) Four Zircaloy-2 Tubes Having Encapsulated Cobalt Targets Sealed Within
.teload E Fuel Bundles Have a Special Central Fuel Rod To Which the Bundle Spacers are Fixed.
In Addition, 'No of the Interior Bundle Fuel Rods Are Removable Special Rods Have Depleted Uranium
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