ML16256A213

09 to Final Safety Analysis Report, Chapter 4, Reactor, Section 4.4, Figures 4.4-1 Through 4.4-11

ML16256A213
Person / Time
Site:	Waterford
Issue date:	08/25/2016
From:	Entergy Operations
To:	Office of Nuclear Reactor Regulation
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References
W3F1-2016-0053
Download: ML16256A213 (14)

Text

0.666 0.898 1.102 1.190 0.960 1.227 1.117 1.226 Assy. Avg. Rod Radial Power Factor Assy. Maximum Rod Radial, Power Factor r 0.667 1.055 0.599 0.833

-0.991 1.132 0.956 0.949 0.991 1.090 1.086 1.094 1.055 1.155 1.002 1.106 1.030 1.133 0.667 0.812 0.949 0.984 1.077 1.061 1.115 1.055 0.923 1.078 1.084 1.175 1.165 1.196 0.599 0.956 0.949 0.980 1.077 1.072 1.144 1.105 0.991 1.090 1.078 1.080 1.182 1.178 1.232 1.212 0.833 1.132 0.984 1.077 1.075 1.156 1.129 1.184 1.084 1.182 1.181 1.249 1.238 1.264 0.960 1.227 1.077 1.175 1.072 1.178 1.144 1.232 1.156 1.136 1.203 1.160 1.249 1.246 1.286 1.271 1.117 1.226 0.949 1.086 0.991 1.094 1.055 1.155 1.061 1.165 1.129 1.203 1.170 1.226 1.238 1.286 1.281 1.299 1.002 1.030 1.115 1.105 1.184 1.160 1.226 1.417 1.106 1.133 1.196 1.212 1.264 1.271 1.299 1.550 0.666 1.102 0,898 1.190 LOUISIANA POWER LIGHT CO.

Waterford Steam Electric Station CORE WIDE PLANAR POWER DISTRIBUTION FOR DNB ANALYSIS Figure 4.4-l

LINE OF SYMMETRY ROD RADIAL POWER FACTOR LINE OF ENGINEERING SYMMETRY ENTHALPY RISE FACTOR APPLIED PITCH AND BOW TO THESE RODS FACTORS APPLIED TO THIS LOUISIANA Figure POWER LIGHT CO.

ROD RADIAL POWER FACTORS IN HOT ASSEMBLY Waterford Steam FOR SAMPLE DNB ANALYSIS 4.4-2 Electric Station

FOR DNB CALCULATIONS 1.26 PEAK 0.2 0

I I

I I

I I

I I

I 0

10 20 30 40 50 60 70 80 90 100 FRACTION OF ACTIVE CORE HEIGHT FROM INLET LOUISIANA POWER LIGHT CO.

Figure Waterford Steam TYPICAL POWER DISTRIBUTIONS 4.4-3 Electric Station

EXIT VOID FRACTION, %

EXIT QUALITY, %

I l

I I

I I

I I

0.

I I-l

-0 I

I 0

16 0

0.0 0.0 0.0

-15

-15

-14 0.0 0.0 0.0

-14

-14

-14 0.0 0.0 0.0

-13

-14

-13 0.0 0.0 0.0

-13

-13

-13 0.0 0.0 0.0

-13

-13

-10 LOUISIANA POWER LIGHT CO.

Waterford Steam Electric Station AVERAGE VOID FRACTIONS AND QUALITIES AT THE EXIT OF DIFFERENT CORE REGIONS Figure 4.4-4

0.8 0

- 1 0 Lu

- 2 0 3

- 3 0

- 4 0 0.2 0.4 0.6 0.8 1.0 FRACTION OF ACTIVE CORE HEIGHT AXIAL DISTRIBUTION OF VOID FRACTION AND QUALITY I

IN THE SUBCHANNEL ADJACENT TO THE ROD I

4.4-5 WITH MINIMUM DNBR LOUISIANA POWER & LIGHT CO.

Waterford Steam Electric Station

MAIN FLOW BYPASS FLOW BYPASS PATHS

1. THRU OUTLET NOZZLE CLEARANCES

2. THRU ALIGNMENT KEY-WAYS

3. THRU SUPPORT CYLINDER HOLES

4. THRU CORE SHROUD CLEARANCES

5. THRU EMPTY GUIDE TUBES

6. THRU RODDED GUIDE TUBES

7. THRU INSTRUMENTED CENTER GUIDE TUBES LOUISIANA POWER LIGHT CO.

I REACTOR VERTICAL ARRANGEMENT Figure Waterford Steam SHOWING BYPASS FLOW PATHS 4. 4 - 6 Electric Station

I STEAM GE No. 1 STEAM GENERATOR No. 2 PUMP No.

PUMP No. 2A PRESSURIZER VESSEL LOUISIANA POWER & LIGHT CO.

Waterford Steam ISOMETRIC VIEW OF REACTOR COOLANT SYSTEM Figure 4.4-7 Electric Station I

WSES-FSAR-UNIT-3 Revision 11 (05/01)

 (DRN 01-416)

Figure 4.4-8, Sheet 1 has been incorporated by reference in accordance with NEI 98-03.

Figure information can be found in Drawing G167, Sheet 1.

 (DRN 01-416)

WSES-FSAR-UNIT-3 Revision 12 (10/02)

¨(DRN 02-1016)

Figure 4.4-8, Sheet 2 has been incorporated by reference in accordance with NEI 98-03.

Figure information can be found in Drawing G167, Sheet 2.

(DRN 02-1016)

WSES-FSAR-UNIT-3 Revision 11 (05/01)

 (DRN 01-416)

Figure 4.4-8, Sheet 3 has been incorporated by reference in accordance with NEI 98-03.

Figure information can be found in Drawing G167, Sheet 3.

 (DRN 01-416)

WSES-FSAR-UNIT-3 Revision 12 (10/02)

¨(DRN 02-1016)

Figure 4.4-8, Sheet 4 has been incorporated by reference in accordance with NEI 98-03.

Figure information can be found in Drawing G167, Sheet 4.

(DRN 02-1016)

NONUNIFORM LATERAL POWER DISTRIBUTION 84 IN. H I

PRESSURE AVG. EXIT QUALITY RUN TYPE

-0.08 TO CHF 2300

-0.59 TO -0.46 HIGH HEAT FLUX (BELOW CHF) 2000

-0.06 TO CHF 4

8 12 16 20 PREDICTED TOTAL PRESSURE DROP, PSI LOUISIANA POWER LIGHT CO.

Waterford Steam Electric Station PRESSURE DROP PREDICTIONS FOR A BUNDLE Figure

2.3 I

I OF DESIGN MINIMUM FLOW 2300 2250 1.9 2200 545 550 555 560 REACTOR INLET COOLANT TEMPERATURE, 2.4 I

4 105% OF DESIGN MINIMUM FLOW 2.2 2300 2250 2200 2.0 I

I 545 550 555 560 REACTOR INLET COOLANT TEMPERATURE, 2.5 I

I 110% OF DESIGN MINIMUM FLOW 2.3 2.1 I

I 545 550 555 560 REACTOR INLET COOLANT TEMPERATURE, LOUISIANA POWER LIGHT CO.

Figure SENSITIVITY OF MINIMUM DNBR TO SMALL Waterford Steam CHANGES IN COOLANT CONDITIONS 4.4-l 0 Electric Station

Revision 11 (05/01)

Waterford Steam Electric Station #3 VALVE & LOOSE PARTS MONITORING SYSTEM SCHEMATIC Figure 4.4-11