ML20154H525

Amend 90 to License DPR-6,allowing Inclusion of All Reloads of I Fuel Design in Tech Specs

ML20154H525
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/17/1988
From:	Muller D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154H517	List: ML20154H514 ML20154H525 ML20154H534
References
NUDOCS 8805250384
Download: ML20154H525 (5)

Text

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CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET NO. 50-155 AMEN 0 MENT TO FACILIY OPERATING LICENSE Amendment No. 90 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 December 14, 1987, 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; I

The facility will operate in conformity with the application, 1

8. i the provisions of the Act, and the rules and regulations of the '

Commission; C. There is reasonable assurance (i) that the activities authorized I 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 l defense and security or to the health and safety of the public; and l

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.

8805250384 880517 PDR ADOCK 05000155 p PDR

t i 2. Acccrdingly"'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 raad as follows:

} Technical Specifications l

! The Technical Specifications contained in Appendix A, as 4 revised through Amendment No. go , are hereby incorporated

! in the license. The licensee shall operate the facility l in accordance with the Technical Specifications. 7 4

3, This license amendment is effective as of the date of its issuance. '

FOR THE NUCLEAR REGULATORY COMMISSION  ;

I:

w  ;

} Daniel R. Muller, Acting Director  !

4 Project Directorate III-1 "

Division of Reactor Projects - III, IV, V i

& Special Projects l

Attachment:

Changes to the Technical l Specifications  ;

I l Date of Issuance: May 17, 1988 l

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ATTACHMENT TO LICENSE AMENDMENT N0. 90 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 5-9a 5-9a 5-9c 5-9c

- . _ _ _ - _ _ _ _ ~. _ . _ _ _ . .._ __ _

TABLE 1 1

Roload G Roloed  ;

Reloads Including Reload G3/G4/H1/ Reload  !

F & Fodified F c13/G14 G1U H2/H3/H4 I Fuel t 4

l Minimum Critical Power i i Ratio at Normal operation 1.59 1.59 1.59 1.59 1.61 Conditions * (1) $

J

Mininum Bundle Dryout Time ** Figure 1 - - - -

j Maximum Heat Flux at;  !

j Overpower. Ptu/h-Ft' (1) 500,000 395,000 407,000 392,900 392,900 -

l Maximum SteadyzState Heat Flux, Btu /h-ft' (1) 410,000  !

324,000 333,600 322.100 322,100 '

Maxieue Average Planar Linear Heat Generation Rate, Steady State, kV/Ft*** (1) Table 2 Table 2 Table 2 Table 2 Table 2 Maximur Bundle Power, gW (1) Fig. 2 x 0.95 Fig. 2 Fig. 2 Fig' 2 FiF. 2 ,

Stability Criterior: Max.

Measured Zero-to-Peak

, Flux Amplitade, Percent l of Average Operating Flux 20 20 20 20 I

20

Maximur Steady-State l Power Level. W, (2) 240 240 240 240 240 1

i Maximum Value of Average ,

2 Core Power Density 46 46 46 46

G 240 MWg , kW/L 46 1

1 Foeinal Feactor Pressure 4

During Steady-State Power 1,335 1,335 1,335 l Operation, Psig 1.335 1,335 Minimut Recirculation Flev Rate Lb/h 6 x 10 0 6 x IC^ 6 x 10 0 6 x 10 6 6 x 10 6 i  ;

Rate of Change of Reactor Power During Power Operation:

Control rod withdrawal during power operation shall be such ths.t the average rate of

, change of reactor power is less than 50 MW 1 less than 20 MW perminutewhenpowerisbetween120MWper minute when power is less than 120 MW,,

g and 200 PV , and 10 MW, per -

] ninute when power is between 200 MW and 240 rfV .

{ *The bundle Minimum Critical Power Ratio (MCPR), based on the Exxon Nuclear

] Corporation XN-2 Critical Power Correlation, rust be above this value. '

1

• • The actual dry out time for CE 9x9 fuel (based on the General Electric Dryout

) Correlation for Nonjet Pump Boiling Water Reactors, NEDE-20566) should be above  !

the dryout time shown in FiFure 1. i i 8**For operation with only one recirculation loop in service these limits shall be '

l reduced by 5 percent for Reload F and Modified F and reduced by 20 percent for  !

i, other fuel types. ,

5-9a Amendment No. 61, 69 SI, 89,90 j

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TABLE 2 MAPLHGR (KW/FT) LIMITS

• Planar Average Reload Reload Recon-Exposure Modi- Reload Reload Reload G3/G4/ Reload Reload stituted Reload (MVD/STM) fled F F G CIU H1 H2 H3/H4 G13/C14 I Fuel --

0 - - - -

7.21 7.0 6.77 -

6.92 200 9.5 9.4 - - - - - -

7.28 360 - - - -

7.62 - - - -

1,000 - - - -

7.95 7.8 7.56 -

7.65 1,630 - - -

7.56 7.81 - - - -

3,810 - - -

7.57 - - - - -

3,900 - - - -

7.65 - - -

7.95 5,000 9.9 9.7 - - - - - - -

6,440 - -

7.28 - - - - - -

6,620 - - - 7.50 7.48 7.48 7.48 -

7.89 10,000 9.9 9.7 - - - - - - -

12,880 - -

7.17 - - - - - -

13,520 - - - -

7.49 - - -

8.00 13,610 - - -

7.56 - - - - -

15,000 9.8 9.6 - - - - - - -

19,050 - - 7.11 - - - - -

7.89 20,000 8.7 8.6 - - - - - - -

20,320 - - - -

7.56 7.56 7.56 - -

20,870 - - -

7.78 - - - -

7.76 24,580 - -

6.84 - - - - - -

25,000 8.4 8.3 - - - - - - -

26,400 - - - -

7.32 7.32 7.32 -

7.19 26,760 - - -

7.64 - - - - -

28,210 - -

6.08 - - - - - -

30,000 7.4 7.3 - - - - - 6.0 6.97 31,210 - - - -

6.73 6.73 6.73 - -

32,000 7.0 6.9 - - - - -

6.0 -

33,020 - - -

7.12 - - - -

6.81 33.380 - - - -

6.69 6.69 6.69 - -

34,000 6.5 6.5 - - - - -

6.0 -

34,470 - -

5.73 - - - - -

6.73 36,000 6.2 6.1 - - - - -

6.0 -

36,290 - -

5.73 - - - - - -

38,000 - - - - - - -

6.0 -

40,000 - - - - - - -

6.0 -

41,400 - - - - - - - 6.0 -

OMAPLHCR ratios shall include the uncertainty listed on Table 3.

5-9c Amendment No. '6I, 62 BJ , 87,90

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