ML20054B253
| ML20054B253 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/08/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054B240 | List: |
| References | |
| NUDOCS 8204160434 | |
| Download: ML20054B253 (5) | |
Text
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UNITED STATES y g. [f.
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c CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. -53 License No. DPR 6
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The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Consumers Power Company s
(the licensee) dated December 15, 1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the-provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be-conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the commonf defense and security or to the health and safety of the public-;
and E.
The issuance of this amendment is in accordance with'10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
G 8204160434 820408 PDR ADOCK 05000155 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Facility Operating License No. DPR-6 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 53..are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
f 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
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Dennis M.
c'h h f Operating Reactors Branch #5 N
Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 8,1982 l
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1 ATTACHMEf!T TO LICEllSE AMEf4DMEf1T fl0. 53 FACILITY OPERATIrlG LICEf1SE fl0. DPR-6 DOCKET fl0. 50-155 Revise Appendix A Technical Specifications by removing the.pages identified below and inserting the enclosed pages. The revised pages include the captioned amendment number and marginal lines indicating the area of change.
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~5-9a
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TABLE 1 Reload Reloads:
Reload G-3/G-4/
F & Modified F Reload G-G-1U H-1/H-2 Minimum Critical Heat Flux Ratio at Normal Operating Conditions
- 3.0 3.0 3.0 3.0 Minimum Bundle Dry Out Time **
Figure 1 Maximum Heat Flux at Overpower, Btu /h-Ft2 500,000 395,000 407,000 392,900 Maximum Steady State Heat Flux, Btu /h-Ft2 410,000 324,000 333,600 322,100 Maximum Average Planar Linear Heat Generation Rate, Steady State, kW/Ft***
Table 2 Table 2 Table 2 Table 2 Maximum Bundle Power, MW Figure 2 x 0.95 Figure 2 Figure 2 Figure 2 g
Stability Criterion: Maximum Measured Zero-to-Peak Flux Amplitude, Percent of Average 20 20 20 20 Operating F. lux Maximum Steady State Power 240 240 240 240 Level, MW Maximum Value of Average Core Power Density @ 240 MW, kW/L 46 46 46 46 g
Nominal Reactor Pressure During Steady State Power Operation, Psig 1,335 1,335 1,335 1,335 Minimum Recirculation Flow Rate Lb/h 6 x 106 6 x 106 6 x 106 6 x 106 Rate-of-Change-of-Reactor-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 MW per minute when power is less than 120 MW, less than 20 MWg per minute when power is between 120 MW and 200 MW, and g
g 10 MW per minute when power is between 200 MWg and 240 MW g
- The bundle Minimum Critical Heat Flux Ration (MCHFR), based on the Exxon Nuclear Corporation Synthesized Hench-Levy Correlation, must be above this value.
- The actual dry out time for GE 9x9 fuel (based on the General Electric Dry Out Correlation for non-jet Pump Boiling Water Reactors, NEDE-20566) should be above the dry out time shown in Figure 1.
M or operation with only one recirculatica loop in service these limits shall be Freduced by 5 percent for Re-load F and Modified F and reduced by 20 percent for other fuel types.
5-9a Amendment No.10, 35, J6, A4, 48', 53
TABLE 2 MAPLHGR(KW/FT) LIMITS Planar Average Exposure Reload Reload Reload Reload (MWD /STM)
Modified F Reload F Reload G G-1U G-3/G-4/H-1 H-2 7.21 7.0 0
200 9.5 9.4 7.62 360 7.95 7.8 1,000 7.56
,7.81 1,630 7.57 3,810 7.65 r
3,900 5,000 9.9 9.7 7.28 6,440 7.50 7.48 7.48 6,620 10,000 9.9 9.7 7.17 12,880 7.49 13,520 7.56 13,610 15,000 9.8 9.6 7.11 19,050
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20,000 8.7 8.6 7.56 7.56 20,320 7.78 20,870 6.84 24,580 25,000 8.4 8.3 7.32 7.32 26,400 7.64 26,760 6.08 28,210 30,000 7.4 7.3 6.73 6.73 31,210 32,000 7.0 6.9 7.12 33,020 6.69 6.69 33,380 34,000 6.5 6.5 5.73 34,470 36,000 6.2 6.1 5.73 36,290 l
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