ML20134E311

Proposed Tech Specs Implementing Reactor Operating Limits for Reload I1 Fuel

ML20134E311
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	08/16/1985
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20134E286	List: ML20134E284 ML20134E301 ML20134E311
References
NUDOCS 8508200148
Download: ML20134E311 (3)

Text

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i ATTACliMENT Consumers Power Company Big Rock Point Plant Docket 50-155 l

PROPOSED TECilNICAL SPECIFICATION PAGE CHANGES August 16, 1985 2 Pages 8500200148 DR 050016 p ADOCK 05000155 PDR Ic0885-0258-NLO4

I.. ..

43 l TABLE 1 l R31ccd G Reload l Reloads Including Reload G3/G4/H1/ Reload F & Modified F G13/G14 G1U H2/H3/H4 II l Minimum Critical Power l Ratio at Normal Operation 1.59 1.59 1.59 1.59 1.59 Conditions *

)

l Mi:imus Bundle Dryout Time ** Figure 1 - - - -

l MaximusHeatFluxag Ov:rpower, Btu /h-Ft 500,000 395,000 407,000 392,900 392,900 l Maximus SteadygState Heat Flux, Btu /h-ft 410,000 324,000 333,600 322,100 322.100 l Maximus Average Planar Linear He:t Generation Rate, Steady State, kW/Ft*** Table 2 Table 2 Table 2 Table 2 Table 2 l Maximus Bundle Power, MW Fig. 2 x 0.95 Fig. 2 Fig. 2 t Fig. 2 Fig. 2 l

l St:bility Criterion: Max.

j Me::ured Zero-to-Peak Flux Amplitude, Percent cf Average Operating Flux 20 20 20 20 20 Maximum Steady-State Power Level, MW, 240 240 240 240 240 Maximum Value of Average Coro Power Density 46 46 46 46 46 8 240 Wg, kW/L Nominal Reactor Pressure .

l During Steady-State Power 1,335 1.335 1,335 1,335 1,335

) Oper tion, Pais l

l Minimum Recirculation l Flow Rate Lb/h 6 x 10 6 6 x 10 6 6 x 10 6 6 x 10 6 6 x 10 6 l

l Rato of Change of Reactor Power During Power Operation l

C:: tral rod withdrawal during power operation shall be such that the average rate of j

chang 3 of reactor power is less than 50 MW, per minute when power is less than 120 MW '

1000 than 20 MW e per mir:towhenpowIrisbetween200MW,and240MW.per g minute when power is Betwee g t

• Th3 bundle Minimus Critical Power Ratio (MCPR), based on the Exxon Nuclear C:rporation XN-2 Critical Power Correlation, must be above this value.

CiThe actual dry out time for GE 9x9 fuel (based on the General Electric Dryout C:rrelation for Nonjet Pump Boiling Water Reactors, NEDE-20566) should be above th3 dryout time shown in Figure 1.

CC0F r operation with only one recirculation loop in service these limits shall be r:duced by 5 percent for Reload F and Modified F and reduced by 20 percent for cther fuel types.

Proposed TSB0885-0258-NLO4 l

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43a TABLE 2 MAPLHGR (KW/FT) LIMITS Planar Average Reload Reload Recon-Exposure Modi- Reload Reload Reload G3/G4/ Reload Reload stituted Reload (MWD /STM) fied F F G G1U Hi H2 H3/H4 G13/G14 II O - - - -

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 - - - - - - -

l 20,320 - - - -

7.56 7.56 7.56 - -

20,870 - - -

7.78 - - - -

7.76 l 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 - -

l 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 -

l J

Proposed l

TSB0885-0258A-NLO4

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