ML19347A499
| ML19347A499 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/10/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347A498 | List: |
| References | |
| FOIA-80-162 NUDOCS 7904260034 | |
| Download: ML19347A499 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION UNITE D STATES y s'
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CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No. DPR-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Consumers Power Company (the A.
licensee) dated March 28, 1979, 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 (1) 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.
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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:
(2) Technical Specifications The Technical Specifications contained in Appendix A. as revised through Amendment No. 26, are hereby incorporated in the license. The licensee shall operate the f acility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMt11SS10H s
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>%u-i Dennis L. Ziemann, C ef Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 10,1979
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ATTACHMENT TO LICENSE AMENDMENT NO. 26 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT Table 1 5-9a (Table 1)
Table 2 5-9b (Table 2)*
Figure 1 5-10 (Figure 1)*
Figure 2 5-11 (Figure 2)*
5-12 (Figure 3)
- These pages are included only for the purpose of assigning page numbers.
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TABLE 1 Reloads:
Reload Reload Modified F & J-2 Reload G G-lU G-3 Mini =um Critical Heat Flux Ratio at Normal Operating. Conditions" 3.00 3 00 3.00 3.00 Mini =um Bundle Dry Out Time **
Figure 1 Figure 2 Figure 2 Figure 2 Maximu=geatFluxatOverpower,-
3;3,000 h07,000 392,900 Btu /h-Ft 500,000 Maxi =um Steady State Heat Flux, Btu /h-Ft2 h10,000 32h,000 333,600 322,100 Maximum Average Planar Linear Heat Generation Rate, Steady State, kW/Ft***
Table 2 Table 2 Table 2 Table 2 Maximun Bundle Power, MW Figure 3 Figure 3, Figure 3 Figure 3l t
Stability Criterien: Maximum Measured Zero-to-Peak Flux A=plitude, s_
Percent of Average Operating Flux 20 20 20 20 Maxi =um Steady 3 tate Power Level, MW 2h0 2k0 2h0 2h0 t
Maximu= Value of Average Core Power Dznsity 6 2h0 MW, kW/L h6 h6 h6 h6 Nc=inal Reactor Pressure During Steady State Power Operation, Psig 1335 1335 1335 1335 Minimu= Recirculatien Flev Rate, Lb/h 6 x 10 6 x 10 6 x 10 6 x 10 Rate-of-Change-of-Reactor Power During Power Operation:
Control rod withdrawal during power operation shall be such that the average rate-of-chtnge-of-reactor cover is less than 50 FM per minute when power is less than 120 MW,
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less than 20 MW Per minute when power is between 120 and 200 MW, and 10 MW P*#
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t minute when pcver is between 200 and 2h0 MW.
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0The bundle Mini =um Critical Heat Flux Ratio (MCHFR), based on the Exxon Nuclear
. Corporation Synthesized Hench-Levy Correlation, must be above this value.
'OThe actual dry out time for each bundle (based on the General Electric Dry Out sm-Correlation for Nonjet Pump Boiling Water Reactors, NEDE-20566) should be above the dry out time shcun in Figure 1 or 2, as appropriate.
- Tc be determined by linear extrapolat '.on fren Table 2.
5-9a Amendment No. 79, 75, 26 m
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3 TA3LE 2_
MAPLHGR (kW/Ft) LIMITS _
Pla.ar Reload Reload Reload G -
Reload G-10 Reload G-3 Average Exposure
(!Nd /STM)
Modified F F,J-2
'6.h53 6.h91 6.554 0
200 95 9.h 6.758 6.750 6.807 21h 216 6.887 6.888 6 973 h37 hk3 6.960 88L 6.978 7 033 885 893 6 929 1,758 6.970 6.98h 1,769 1,773 6.885 6.913 3,494 6.983 3,509 3,5h5 97 99 6.838 6.865 5,000 6,939 6 978 6,970 7,085 97 99 6.8h7 6.882 10,000 10,h22 10,L82 7 019 10,690 6.867 6.90h 13,938 7.069 1L,C19 1L,355 9.8 9.6 15,000 8.6 8.7 20,000 6.905 6.958 21,022 7.171 21,19L 21,8h3 8.3 8.h 25,000 6.8h3 6.903 27,775 7 161 28,c35 29,oSL 6.703 6.923 3L,C13 6.958 l
35, S 7 35,2R AmendmentNo.IU,48,26 5-9b
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d Q = MAPLHGR LIMIT X w
NUMBER OF ACTIVE FUEL RODS l
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N 700 800 900 TOTAL BUNDLE PEAK LINEAR HEAT GENERATION RATE. Q (KW/ FT) 4 Figure 1 l
FUNCTION T(Q) FOR ENC 11X11 FUEL
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POWER VOlO RELATION
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800 700 6no TOTAL BUNDLE PEAK LINEAR HEAT GENERATION RATE Q(KW/F)00 Figure 2 FUNCTION TCQ) FOR GE 9 X 9 FUEL POWER VOID RELATION Amendment No. /E, T6 1
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2.20 3 08 3 0S 3.0E 3 03 2.20 3 52 h.18 h.ho h.ho L.16 3 52 2.20 3 52 h.1S h.Lo 3.76 h.13 L.ho L.15 3.h7 2.20 3.06 h.18 L.ho L.Lo h.ho h.ho L.Lc L.ho L.18 3.oS 3.oS L.ho h.13 h.ho L.2h L.2h L.ho E.13 h.ho 3.0S 3.CS h.Lo L.13 h.Lo L.2h h.2h h.ho h.13 L.ho 3.08 3 08 h.18 L.Lo L.ho L.ho h.ho L.ho L.ho L.16 3.05 2.20 3.52 h.1S L.Lo L.13 h.13 h.ho L.16 3.52 2.20 3.52 h.18 L.Lo L.ho h.18 3 52 2.20 3.08 3 08 3 0S 3 08 2.20 Figure 3 Maxt~.u. Bun 11e ?cuer, 13 P00R ORIGINAL e-m Amendment No. 26