ML20050E122
| ML20050E122 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/09/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20050E121 | List: |
| References | |
| NUDOCS 8204130050 | |
| Download: ML20050E122 (8) | |
Text
.
a reg 4
ji, UNITED STATES h.'*
NUCLEAR REGULATORY COMMISSION o
aC WASHINGTON, D. C. 20555
,o$
Q CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. DPR-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated February 25, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
i e
B204130050 010609 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.
OPR-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 44, are hereby incor-porated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION c
e Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 9,1981
+
O
ATTACHMENT TO LICEllSE AMENDMENT NO. 44 J
FACILITY OPERATING LICENSE NO. DPR-6 DOCKET fl0. 50-155 Revise the Technical Specifications by removing the following pages and i
inserting the enclosed pages. The revised pages are identified by the
~
captioned amendment number and contain vertical lines-indicating the areas of change.
1 i
PAGES l'
5-9a
~
5-9b 5-10 (Blank) 5-11 l
5-12
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9 i
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TABLE I Reloads:
Reload Reload F & Modified F Reload G G-1U G-3/G-4 Minimum Critical Heat Flux Ratio at Normal Operating Conditions
- 3.0 3.0 3.0 3.0 l
Minimum Bundle Dry Out Time **
Figure 1 Maximum Heat Flux at Overpower, Btu /h-Fta 500,000 395,000 407,000 392,900 Maximum Steady State Heat Flux, Btu /h-Fta 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 c
Stability Criterion: Maximum Measured Zero-to-Peak Flux Amplitude, Percent of Average Operating Flux 20 20 20 20 Maximum Steady State Power Level, MW 240 240 240 240 g
Maximum Value of' Average Core Power Density @ 240 MW, kW/L 46 46 46 46 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 operat, ion shall be such that the average rate-of-change-of-reactor-power is less than 50 MW per minute when power is less than g
120 MW, less than 20 MWe per minute when power is between 120 MW and 200 MW, and e
g t
10 MW per minute when power is between 200 MW and 240 MW.
g e
e
- 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.
5-9a Amendment No. }0,15,,26, 44
TABLE 2 MAPLHGR (kW/FT) LIMITS Planar Aver. ige Exposure Reload Reload Reload (MWD /STM)
Modified F Reload F Reload G G-1U G-3/G-4 0
7.21 200 9.5 9.4 360 7.62 1,000 7.95 1,630 7.56 7.81 3,810 7.57 3,900 7.65 5,000 9.9 9.7 6,440 7.28 6,620 7.50 7.48 10,000 9.9 9.7 12,880 7.17 13,520 7.49 13,610 7.56 15,000 9.8 9.6 19,050 7.11 20,000 8.7 8.6 20,320 7.56 20,870 7.78 24,580 6.84 25,000 8.4 8.3 26,400 7.32 26,760 7.64 28,210 6.08 30,000 7.4 7.3 31,210 6.73 32,000 7.0 6.9 33,020 7.12 33,380 6.69 34,000 6.5 6.5 34,470 5.73 36,000 6.2 6.1 36,290 5.73 d'
s t
5-9b Amendment No. W. M. J6, 44 I
(Deleted) -- previously designated Figure 1 5-10 Ameridment }(,J4, 44 0
2.5 2.0 E
S T
G Z
N g 1.5 ca g
8 Q = !!APU:GR Ll.'ll T X aw NU!.!BER OF ACTI'/E FUEL ROOS 1.0
/
"N 600 700 800 TOTAL SU!!DLE FEAK LINEAR HEAT GENERATION RATE G(KW/FT) 1 FIGURE 1 l
FUl?CTIC:t T(0) FGR GE S X S FUEL l
PO?!ER '/010 REL.\\ TIC :
l 5-11 Amendment No.15', gf/, 44
NCRTH 2.30 3.22 3.22 3.22 3.22
~2.30 3.69 h.00 h.00 h.00 h.00 3.69 2.30 3.69 h.co h.00 3.9h h.00 h.00 h.00 3.63 2.30 3.22 h.00 h.00 h.00 h.00 h.00 h.C0 h.00 h.00 3.22 3.22 h.00 h.00 h.00 h.00 h.C0 h.C0 h.00 k.00 3.22 3.22 h.00 h.00 h.00 h.00 h.00 h.00 h.co h.00 3.22 3.22 h.00 k.00 h.00 h.00 h.00 h.00 h.00 h.00 3.22 2.30 3.69 h.00 k.00 h.co h.00 h.00 h.00 3.69 2.30 3.69 h.00 h.00 h.00 h.00 3.69 2.30 3.22 3.22 3.22 3.22 2.30 W
Figure 2 Maximum Bundle ?cwer, MWg 5-12 Amendment No. JAf,44 e
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