ML20132F489

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Proposed Tech Specs,Revising Fuel MAPLHGR Limits,Per 850816 Request,In Order to Implement Operating Limits for Reload I1 Fuel
ML20132F489
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 09/24/1985
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20132F413 List:
References
NUDOCS 8510010338
Download: ML20132F489 (3)


Text

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f ATTACEMEhT Consumers Power Company Big Rock Point Plant Docket 50-155 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES September 24, 1985 8510010338 850924 2 Pages PDR ADOCK 05000155 p PM IC0885-0258-NLO4

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43

, TABLE 1 Reload G Reload Reloads Including Reload G3/G4/H1/ Reload F & Modified F G13/G14 G1U H2/H3/H4 Il Minicum Critical Power.

Ratio at Normal Operation 1.59 1.59 1.59 1.59 1.61 Conditions

  • Minimum Bundle Dryout Time ** Figure 1 - - - -

MaximumHeatFluxag Ovsrpower, Btu /h-Ft 500,000 395,000 407,000 392,900 392,900 Maximum Steady 7 State Heat Flux, Btu /h-ft 410,000 324,000 333,600 322,100 322,100 Maximum Average Planar Linear H::t Generation Rate, Seccdy State, kW/Ft*** Table 2 Table 2 Table 2 Table 2 Table 2 Maximum Bundle Power, MW Fig. 2 x 0.95 Fig. 2 Fig. 2 Fig. 2 Fig. 2 t

Stability Criterion: Max.

Mercured Zero-to-Peak Flux A=plitude, Percent of Average Operating Flux 20 20 20 20 20

. Maximum Steady-State Pow 3r Level, MW g 240 240 240 240 2'40 Maximum Value of Average Cora Power Density 46 46 46 46 46

@ 240 MW g

, kW/I Nrainal Reactor Pressure During Steady-State Power 1,335 1,335 1,335 1,335 1,335 Oparction, Psig Mininum Recirculation Fir.w Rate Lb/h 6 x 10 6 6 x 10 6 6 x 10 6 6 x 10 6 6 x 10 6 Rato of Change of Reactor P;w3r During Power Op;rstion:

C:ntrol rod withdrawal during power operation shall be such that the average rate of ch:nge of reactor power is less than 50 MW per minute when power is less than 120 MWg ,

loca chan 20 MW per minute when power is between 120 MWg and 200 MWg , and 10 MW per cinute when power is between 200 MWgand 240 MWe

  • CThe bundle Minimum Critical Power Ratio (MCPR), based on the Exxon Nuclear Corporation XN-2 Critical Power Correlation, must be above this value, ccThe actual dry out time for GE 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 Figure 1.

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

Proposed TSD0885-0258-NLO4

9 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 GIU Hi H2 H3/H4 G13/G14 Il 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 - - - 3.00 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 -

Proposed TSB0885-0258A-NLO4

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