ML20215C739

Proposed Tech Specs Re Reactor Core & Controls

ML20215C739
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	12/05/1986
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20215C724	List: ML20215C721 ML20215C739 ML20215C760 ML20215C766
References
NUDOCS 8612150372
Download: ML20215C739 (5)

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ATTACHMENT 1 Consumers Power Company Big Rock Point Plant Docket 50-155 i

PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES December 5, 1986 I

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8612150372 861205 PDR ADOCK 05000155 3 Pages p

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l TSB1286-0169-NLO4

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.4, 5.0 REACTOR CORE AND CONTROLS The reactor core and controls shall consist of all the components of the reactor core including the reactor reactivity control system and the liquid poison system. The expected configuration of the core is shown in Figsta 5.1.

5.1 DESIGN FEATURES The dimensions for these design features are for the cold condition and are subject to normal manufacturing tolerances.

5.1.1 Principal Core Materials Fuel (Sintered Pellets or UO r UO -Pu0 2

2 2

Compressed Powder)

Moderator and Reflector Light Water Structural Components (Fuel cladding will, in addition to 304 SS and Incaloy-800, include Zr-2 Inconel-600 and Zr-3Nb-ISn) i Flow Channels Zircaloy 2 and 304 SS Control Rods:

l Neutron Absorbing Material solid Hafnium (Hf) j or Carbide (B C) 4 i

Powder B,.C Cladding Material 304 or 348 SS Dummy Rod / Tube Material 304 or 348 SS Assembly Sheathing Material 304 SS 5.1.2 Control Rod Assemblies The reactor core shall contain 32 control rod assemblies each composed of a cruciform array of empty or solid stainless steel tubes, boron carbide (B C) powder filled stainless tubes and/or 4

solid hafnium (Hf) rods surrounded by a cruciform shaped stainless steel sheath. The individual poison rod composition made up of principal materials boron carbide and/or hafnium shall have an effective poison length of approximately 68 inches.

Proposed TSB1286-0169-NLO4

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.i 43 TABLE 1 Reload G Reload Reloads Including Reload G3/G4/H1/

Reload F & Modified F_

G13/G14 G1U H2/H3/H4 11/12 Minimum Critical Power Ratio at Normal Operation 1.59 1.59 1.59 1.59 1.61 Canditions*

Minimum Bundle Dryout Time ** Figure 1 Maximum Heat Flux ag Overpower, Btu /h-Ft 500,000 395,000 407,000 392,900 392,900 Maximum SteadyyState Heat Flux, Btu /h-ft 410,000 324,000 333,600 322,100 322,100 Maximum Average Planar Linear H ct Generation Rate.

Stocdy State, kW/Ft***

Table 2 Table 2 Table 2 Table 2 Table 2 I*

E'

'E' E*

Maximum Bundle Power, MW E*

E t

Strbility Criterion: Max.

Maccured Zero-to-Peak Flux Amplitude, Percent of Average Operating Flux 20 20 20 20 20 Maximum Steady-State P ver Level, MW, 240 240 240 240 240 Maximum Value of Average Cara Power Density 46 46 46 46 46

@ 240 MW, kW/L g

N=tinal Reactor Pressure During Steady-State Power 1,335 1,335 1,335 1,335 1,335 Op ration, Paig Minimum Recirculation 6

6 6

6 6

Flew Race Lb/h 6 x 10 6 x 10 6 x 10 6 x 10 6 x 10 l

Rito of Change of Reactor

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P war During Power l

Op2 ration:

Control rod withdrawal during power operation shall be such that the average rate of chtnge of reactor power is less than 50 MW, per minute when power is less than 120 MW,,

isse than 20 MW Per minut.e when power is 5etween 120 MW and 200 MW, and 10 MW per' t

t g

g ainute when power is between 200 MW and 240 MW.

t g

• The bundle Minimum Critical Power Ratio (MCPR), based on the Exxon Nuclear Corporation XN-2 Critical Power Correlation, must be above this value.

• • The 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.

• • • For operation with cnly cne recirculation loop in service these limits shall be reduced by 5 percent for Reload F and Modified F and reduced by 20 percent for l

other fuel types.

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2 43n 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' H1 H2 H3/H4 G13/G14 II/I2 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 7.56 7.56 7.56 20,320 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 l

36,290 5.73 38,000 6.0 40,000 6.0 41,400 6.0 Proposed l

l TSB1286-0169-NLO4

o ATTACHMENT 2 Consumers Power Company Big Rock Point Plant Docket 50-155 J

TECHNICAL INFORMATION RELATING TO ALTERNATE FOR MATERIALS FOR BWR - CONTROL ROD - B C - TUBE CLADDING 4

December 5, 1986 20 Pages e

TSB1286-0169-NLO4

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