Text

Submittal of Additional Data for Confirmatory EPU Analyses
	ML090970105
Person / Time
Site:	Saint Lucie
Issue date:	03/23/2009
From:	Katzman E; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2009-069
	Download: ML090970105 (94)
	v • d • e

0 FPL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2009-069 10 CFR 50.4 March 23, 2009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE:

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Extended Power Uprate Data for NRC Confirmatory EPU analyses This letter provides additional data requested by the NRC via emails dated May 28, 2008, and December 7, 2008, that is needed to build PSL-specific LOCA models for the NRC's confirmatory EPU analyses. This data is provided in Attachments 1 and 2.

Please contact Ken Frehafer at 772-467-7748 or Kathy Rydman at 772-467-7680 if there are any questions regarding this information.

Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant ESKJKWF Attachments A-0ol an FPL Group company

L-2009-069 Page 1 of 44 ST. LUCIE UNIT 1 EPU Input Data Request to NRC for LOCA Model Item Parameter -Description Units Value Comments No.

1.

Plant Operating Conditions 1 a For rated power conditions (Current)

1. Primary and Secondary Flow rates:

1.1. Core flow Unc: +/- 14,945 gpm and gpm 410,922 min flow is 365,000 gpm 1.2. Main coolant pumps 95,000 (IAl) gpm 96,000 (1A2)

RCP Pump Test Data gpm95,000 (1IB1) 94,000 (1B2) 1.3. Steam flow Ibm/s See Item I a.7.1 1.4. Feedwater flow Ibm/hr See Item la.7.1 1.5 SG recirculation ratio/boiler section Power

%Circ flow Ratio Power-25 15.3 50 8.7

% CircRatio 75 5.95 90 4.9 100 4.3

2.

Primary and Secondary Pressures:

2.1. Pressurizer Pressure range is 2225 to psia 2250 2275, with Unc: +/- 22 Normal, + 80 Accident

L-2009-069 Attachment I Page 2 of 44 Item Parameter -Description Units Value Comments No.

2.2. Core inlet Estimate based on Rx psia 2285 vessel pressure losses of 35.4 psia and core outlet pressure.

2.3. Core outlet Assumed to be the same as psia 2250 the pressurizer.

2.4. Reactor coolant pump discharge Assume a I psi pressure psia 2286 drop from RCP discharge to core inlet.

2.5. Steam generator dome Steam Generator Outlet psia 861.5 from Benchmarked Heat Balance plus pressure drop to Upstream Outlet Nozzle 2.6. Turbine control valve inlet psia See Item I a.7.3 2.7. Detailed primary loop pressure drop From Cycle 15 data and distribution psi Table 14 0%SG tube plugging.

3.

Primary and Secondary Temperatures:

3.1. Hot leg Assumed to be the same as the core outlet temperature OF 599 since the Rx vessel does not have upper head injection.

3.2. Cold leg OF 549 Tcold temperature at full Unc: +/- 3'F power.

3.3. Core outlet OF 599 3.4. Upper Head Assumed to be the same as OF 599 the core outlet temperature since the Rx vessel does

L-2009-069 Page 3 of 44 Item Parameter -Description Units Value Comments No.

not have upper head injection.

4.

Water levels in the pressurizer and steam L*

i{

i 4**

generators.

4.1. Pressurizer

% Tap Span See Figure 1 4.2. Steam Generators Reference SG elevations ft 35.0 from bottom of support skirt base.

5. Leakage flows (Bypass):

% of vessel flow 5.1. Outlet nozzle clearances percent 1.18 5.2. Downcomer to upper head percent 0.17 5.3. CEA shrouds Equivalent to a fraction of the leakage through guide percent N/A tubes (item la.5.5.1). This has not been quantified.

5.4. Upper head to upper plenum (guide This has not been structure holes) percent N/A quantified.

5.5. Core bypass (guide tubes, barrel-5.5.1. G u i d e t u b e sp e c n1

. 6-5.5.2. Barrel-baffle percent 0.50

L-2009-069 Page 4 of 44 Item Parameter -Description Units Value Comments No.

6.

Steam generator recirculation ratio Power-

%Circatio See Item la.l.5

%CircRatio

7.

Heat balance information, such as:

7.1. Feedwater and steam flows lbm/hr 11,851,050 Benchmarked Heat 11,784,590 Balance 7.2. Feedwater temperature 0F 435 Benchmarked Heat Balance 7.3. Turbine inlet pressure Benchmarked Heat psia 816.4 Balance, Turbine Valve Inlet

1.

Plant Operating Conditions 1b.

For EPU conditions.

1. Primary and Secondary Flow rates:

1.1. Core flow Nominal value based on the most recent gpm 410,922 measurement. Unc: +

15,000 gpm; TS Min flow is 375,000 gpm 1.2. Main coolant pumps 95,000 (1Al) gpm 96,000 (1A2)

RCP Pump Test Data 94,000 (1B2) 1.3. Steam flow Ibm/s See Item 1b.7. l 1.4. Feedwater flow Ibm/hr See Item I b.7. I 1.5. SG recirculation ratio/boiler section flow Power-Power

%Circ Ratio

% CircRatio 25 14.18

L-2009-069 Attachment I Page 5 of 44 Item Parameter'-Description Units Value Comments No.

50 7.92 75 5.32 90 4.38 100 3.89

2.

Primary and Secondary Pressures:

2.1. Pressurizer 2225 to 2275 psia Unc: +/- 40 2.2. Core inlet psia 2285 Assumed to remain similar to current conditions.

2.3. Core outlet psia 2250 Assumed to remain similar to current conditions.

2.4. Reactor coolant pump discharge psia 2286 Assumed to remain similar to current conditions.

2.5. Steam generator dome psia 864.6 2.6. Turbine control valve inlet psia See Item lb.7.3 2.7. Detailed primary loop pressure drop psi Table 14 Assumes 10% SG tube distribution plugging.

3.

Primary and Secondary Temperatures:

3. 1. Hot leg OF 606.0 Assumes 10% SG tube plugging.

3.2. Cold leg 551 Corresponds to 100%

OF Power. Tcold at 0% power is 532'F.

3.3. Core outlet OF 608.2 Assumes 10% SG tube plugging.

3.4. Upper Head OF 608.2 Assumed to be the same as vessel outlet.

4.

Water levels in the pressurizer and steam generators.

4.1. Pressurizer

% Tap Span See Figure 1 4.2. Steam Generators ft 35.0 Reference SG elevations from bottom of support

L-2009-069 Attachment I Page 6 of 44 Item Parameter -Description Units Value Comments No.

skirt base. Assumes NWL does not change for EPU.

5.

Leakage flows (Bypass):

5.1. Outlet nozzle clearances percent 1.27 5.2. Downcomer to upper head percent 0.18 5.3. CEA shrouds pThis has not been spercent N/A quantified.

5.4. Upper head to upper plenum (guide This has not been structure holes) percent N/A quantified.

5.5. Core bypass (guide tubes, barrel-baffle) 5.5.1. Guide tubes percentGuide and Instrument percento2.00oTubes 5.5.2. Barrel-baffle percentIncludes Core Shroud percen 0.54Bypass

6.

Steam generator recirculation ratio Power-See Item lb.1.5,

%CircRatio

7.

Heat balance information, such as:

7.1. Feedwater and steam flows lbm/hr See Table 15 7.2. Feedwater temperature OF See Table 15 7.3. Turbine inlet pressure psia See Table 15

2.

Analysis Topical Reports See References provided

1. Topical Report on the licensing analysis SeeeCm nt below applicable to rated See power:

of record for LOCA at rated power and Comment Se CXN-NF-82-49(P)(A),

EPU conditions.

Rev. 1, "Exxon Nuclear Company

L-2009-069 Page 7 of 44 Item Parameter -Description Units Value Comments No.

Evaluation Model Revised EXEM PWR Small Break Model",

EMF-2328(P)(A),

"PWR Small Break LOCA Evaluation Model, S-RELAP5 Based",

EMF-2087(P)(A),

"SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications".

e EMF-2514, Rev. 0, "St.

Lucie Unit 1 Large Break LOCA/ECCS Analysis," Dec. 2000.

For EPU, the SBLOCA Topical Report from above will be used. For LBLOCA, the EPU Topical Report is: EMF-2103(P)(A), Rev. 0, "Realistic Large Break LOCA Methodology for PWRs". Analysis results are in the UFSAR.

Safety System Logic, Setpoints and Delay

3.

Times Critical Safety Parameters List (also called "Groundrules document") for the last reload for:

L-2009-069 Page 8 of 44 Item Parameter -Description Units Value Comments No.

1. ESFAS See Table 11 See Table 11 See Table 11

2. RPS See Table 11 See Table 11 See Table 11

3. SGIS/MSIS See Table 11 See Table 11 See Table t1

4.

PORV See Table 11 See Table 11 See Table 11

5. SRV See Table 11 See Table 11 See Table 11

4.

Primary and Secondary Pressure Drops

1. Primary side pressure drop distribution with corresponding flow rate, including leakage Later Later Later flows (from design data or vendor analyses).

2.

Secondary side pressure drop distribution with corresponding flow rate, including Later Later Later leakage flows (from design data or vendor analyses).

5.

Core and Fuel Design

1. Number of assemblies N/A 217

2.

Dimensions Array: 14 x 14, N/A

~~Pitch: 8.18 in, Length: 157.115 in

3.

Spacer grid locations and K-factors K-factors See Table 4 for Core inlet region/ bottom Grid locations, grid = 3.530 N/A Mid-grid 7 spacers = 8.496 See Comments for Outlet region/top grid =

K-factors.

4.63 Bare rod = 3.971

4.

Vessel pressure drops Current values:

_._ Vesselpressuredropspsi a) 6.8 a) Inlet nozzle & 90 degree

L-2009-069 Attachment I Page 9 of 44 Item Parameter -Description Units Value Comments No.

b) 21.5

turn, c) 7.1 b) Downcomer, lower plenum, support structure

& fuel assembly, c) Fuel assembly outlet to outlet nozzle.

5. Bypass and leakage flows

% of total See Comment See items la.5.5 & l.b.5.5 flow above

6. Number and location of fuel rods N/A 176 per Assy.

See Figures 3 and 4 for 38,192 total location.

7. Number and location of guide tubes 4 guide tubes and N/A I instrument tube See Figure 3 for location.

per AssT.

6. Equipment Drawings and Design

oi:=;2 ii!*

Reports To confirm the calculation of flow path lengths Tal 6 and elevations, flow areas, volumes, metal mass and surface areas (including pipe schedules),

dow ncom er.......if..available)................................

and form loss (due to bends, contractions, S

expansions, orifices, etc.) for the following equipment:

4. Reactor vessel and internals (identification of all core bypass flow paths and flow rates, See Table 6 including upper plenum or head to downcomer, if available).

2.

Primary loop piping (hot leg, cold leg, See Table 6 pump suction).

3.

Reactor coolant pumps.

See Table 6

4.

Steam generators and internals (U-tube lengths, separators, inlet and outlet plenum, See Table 6 etc.), (TH Design Report).

I I

I

L-2009-069 Attachment I Page 10 of 44 Item Parameter -Description Units Value Comments No.

5. Pressurizer, surge line, spray lines, safety See Table 6 and relief valves and connecting lines, etc.

6.

Main steam lines out to the turbine stop valves, including safety and relief valves and connecting lines, main steam isolation valves, flow restrictors, etc.

7.

Main feedwater lines from the isolation See Table 6 valves to the steam generator inlet.

8.

Auxiliary feedwater lines and feedwater See Table 6 pump type, configuration and capacity.

9.

Safety injection equipment including SITs, high and low pressure injection systems and See Table 6 connecting piping.

10. Charging and letdown system (CVCS).

See Table 6

11. Residual heat removal system.

See Item 6.9 for LPSI See Comment System. LPSI and RHR are the same system.

7.

Reactor Vessel Internals Dry weight and surface area of reactor vessel internal structures:

1. Core support barrel Includes upper, center, and 103,500 /

lower portions of the core Lbs / sq. ft.

1046 Inside support barrel; upper and 1106 outside lower flange; inner and outer nozzle areas.

2. Core shroud 34,900 /

Includes vertical and Lbs / sq. ft.

590 Inside horizontal surfaces of the 5outside core shroud. Weight includes Tie Rods.

3.

Lower core support plate Lbs / sq. ft.

7,900 / 243 Includes top and bottom

L-2009-069 Attachment I Page 11 of 44 Item Parameter -Description Units Value Comments No.

surfaces; surface areas inside the holes of the plate.

4.

Fuel alignment plate (Upper Core Plate)

Includes top and bottom Lbs /sq. ft.

8,900/238 surfaces; surface areas inside the holes of the plate.

5.

Upper guide structure Includes CEA shrouds with extensions; total UGS plate, beam, &

L bs / sq. ft.

94,4 0 0 / 6 0 40 cy ln er a eas; t cylinder areas; total fuel alignment plate area (Neglects guide tubes).

6.

Core support assembly Includes vertical webs; Lbs /sq. ft.

47,800 1371 flanges; cylinder; columns core support plate (Item 3 above); bottom plate.

7.

Flow skirt Includes top and bottom surfaces; surface areas Lbs /sq. ft.

3,600/292 inside the holes of the plate.

8.

Control element assembly (CEA) shroud 41,300 /

Includes single and double Lbs / sq. ft.

1980 Inside shrouds.

2167 outside

9.

Shroud extensions 3,000 /

Includes single and double Lbs / sq. ft.

386 Inside shrouds.

476 outside

10. Grid assemblies Lbs / sq. ft.

20.60 / 71.2892

8.

Steam Generator Internals

1. Weight of steam generator tube sheet and surface area of tube sheet exposed to

L-2009-069 Attachment I Page 12 of 44 Item Parameter -Description Units Value Comments No.

primary side fluid.

1.1. Weight of Tube Sheet Includes base metal Ibm 94,334 (93,239 Ibm) and cladding (1095 Ibm).

1.2. Area of Tube Sheet (Primary Side) ft2 75 Area for tube sheet only.

2.

Weight and surface area of steam generator wrapper.

2.1. Weight of SG wrapper Assume height of wrapper ibm 25,955 is 21.3 ft and material density is 0.284 Ibm/in3 2.2. Surface area of SG wrapper ft2 Inner: 842 Assume height of wrapper Outer: 850 is 21.3 ft.

9.

Steam Generator Fluid Volumes

1. Inlet plenum ft3 222.026 Including Manway

2.

Outlet plenum fW 3

222.665 Including Manway

3.

Active tubes, Outlet Inactive Tubes, Inlet t3 1129.04 (Active),

Inactive Tubes 36.635 (Outlet),

36.635 (Inlet)

4.

Number of steam generator tubes N/A 8523

5.

Length of shortest and longest tubes ft 50.786 70.981

10.

Steam Generator Parameters

1. Inventory and recirculation ratio versus load Power Secondary (essential at rated power conditions).

Mass Inventory at EPU Im0 214393 conditions. Recirculation 25 178823 ratios provided in Item lb.

50 160630 1.5 75 147181

L-2009-069 Page 13 of 44 Item Parameter -Description Units Value Comments No.

90 140456 100 136456

2.

SG flow areas, K-factors and flows Later Later Later

11.

MS Line Flow Restrictor

1. Restrictor flow area.

0*

36peSG Outlet Nozzle Area 2.5par SG Flow Venturi Area Steam Generator and Reactor Vessel

12.

Heights

1. Volume versus height relationship for the steam generators, with downcomer and ft3 vs. ft See Table 3 boiler regions provided separately.

2.

Volume versus height for the reactor vessel ft3 vs. ft See Table 1 with internals installed.

13.

Reactor Coolant Pump Rated Conditions 21

1. Head ft 273.5

2.

Flow gpm 95,000

3.

Torque lbf-ft 32,750

4.

Speed rpm 886.25

5. Density Derived using values in lbs/ft3 46.90 13.1Y-13.4 above using an average efficiency of.8925

6.

Homologous pump curves (four quadrant)

N/A See Table 5

7.

Pump inertia and friction (coefficients of lbmft2 101,900 polynomial in pump speed)

____1 1 0----

8.

Coolant primary system fluid volume ft3 112 within pump

L-2009-069 Attachment I Page 14 of 44 Item Parameter -Description Units Value Comments No.

9.

RCP metal mass, excluding motor lbs 75,000 Dry Weight

10. Reverse rotation device operational for N/A Yes Device prevents reverse RCPs rotation.

11. Pump power to primary fluid 14.6 MWt MW (nominal),

20 MWt (max)

12. Coastdown characteristics N/A See Figure 2 UFSAR Figure 15.2.5-1

13. Pump trip setpoints N/A Overcurrent Overload Trip.

14. Pump time delays and logic N/A N/A No safety related RCP trips.

14.

Core Cooling System

1. HPSI and LPSI delivery curves See Tables 12 &

gpm 13

2.

SIT total volume ft3 2020

3. SIT initial pressure and liquid volume 215 Minimum TS SIT pressure psia / ft3

/(1090 to 1170)

Nominal liquid volume in "t1 Mode 1.

4. CST minimum capacity gal 110,000

5.

Charging pump flow versus pressure gpm 40 (nominal) to (maximum) 49 Reciprocal pump. Flow is per charging pump.

Nominal value does not include 4 gpm for RCP bleed off.

15.a Control Systems Rated power operation of the primary and secondary control systems for:

1. SG water level instrumentation and control (three-element)

Later Later Later Later Later Later

L-2009-069 Page 15 of 44 Item Parameter -Description Units Value Comments No.

2.

SG pressure (including bypass and ADV)

Later Later Later

3. Pressurizer heaters and sprays Later Later Later

4.

Pressurizer level Later Later Later

5. Auxiliary feedwater Later Later Later

6. CVCS (charging and letdown)

Later Later Later 15.b Control Systems EPU condition operation of the primary and secondary control systems for:

7. SG water level instrumentation and control Later Later Later (three-element)

8. SG pressure (including bypass and ADV)

Later Later Later

9.

Pressurizer heaters and sprays Later Later Later

10. Pressurizer level Later Later Later

11. Auxiliary feedwater Later Later Later

12. CVCS (charging and letdown)

Later Later Later

16.

Reactor Vessel Upper Head

1. Upper head fluid temperature at normal operating conditions.

17.

Essential Valve Characteristics Number of valves, full open flow area, forward/ reverse flow coefficients (CV's),

open/close rate, minimum flow at rated conditions, logic for opening and closing the valves for:

OF Later ISSIIIe LO U[ Me same as core outlet temperature since the Rx vessel does not have upper head injection.

L-2009-069 Attachment I Page 16 of 44 Item Parameter -Description Units Value Comments No.

1. Pressurizer PORVs See Table 2

2.

Pressurizer safety valves See Table 2

3.

Main steam safety valves See Table 2

4.

Atmospheric dump valves See Table 2

5.

TCVs (turbine control valves)

See Table 2

6.

Turbine bypass valves See Table 2

7.

TSVs, (turbine stop valves)

See Table 2

8.

MFIVs See Table 2

9.

MSIVs See Table 2 18 to 20 Reactor Core Parameters

1. Control rod insertion versus time after seconds 3.1 Time for 90% insertion scram.

2.

CEA worth versus insertion (with and without highest worth rod stuck out of Later Later Later core).

3.

Reactivity versus fuel temperature and

F vs Ap See Tables 7 & 8 reactivity versus moderator density.

4.

Moderator temperature coefficient.

F vs Ap See Table 9

5. Typical top peaked axial power profile.

Axial height (ft) vs. Axial See Table 10 Power Shape

6.

Minimum and maximum average fuel clad Later gap conductivity at ratedpower conditions.

7.

Minimum local gap conductance as a Later Later Later function of LHGR.

LaterLaerLate

8.

Gap conductance.

Later Later Later

9.

Linear heat rate.

kW / ft 15.0 (Max)

Value of 6.96 assumes 100

L-2009-069 Attachment I Page 17 of 44 Item Parameter -Description Units Value Comments No.

6.96 (Ave)

SS rods. Without this assumption, the average is 6.94 kW/ft.

10. Fuel average and centerline temperature as a function of burnup for the hot rod in the Later Later Later hot bundle.

21.

Operator Actions During LOCA

1. Reactor coolant pump trips (conditions to Accident analysis assumes trip pumps - automatic or manual)

LOOP concurrent with Pumps LOCA, and pumps are not None automatically trip loaded onto EDGs or on LOOP manually operated. Same assumption for EPU analysis.

2.

HPSI throttling criteria If HPSI pumps are operating, and ALL of the following conditions are satisfied:

° RCS subcooling is greater than or None See Comment equal to minimum subcooling

Pressurizer level is at least 30%

and NOT lowering,

At least ONE S/G is available for RCS heat removal with level being restored to or maintained

L-2009-069 Page 18 of 44 Item Parameter -Description Units Value Comments No.

between 60 and 70% NR,

- Rx Vessel level indicates sensors 4 through 8 are covered, or NO abnormal differences (greater than 20'F) between THOT and Representative CET temperature, Then, THROTTLE SI flow. Same assumption for EPU analysis.

3.

MS line break auxiliary feedwater control.

AFW is manually stopped Min 10 10 minutes after a MSLB event. Same assumption for EPU analysis.

Most recent COLR provided to NRC via FPL

22.

Core Operating Limits Report eSee Comment 1105-2008. EPU COLR to be provided later after it is issued.

23.

RCS Material Property Data For the various materials in the reactor coolant system (stainless steel, inconel, etc.):

1. Density lb/ft3 See Table 16

2.

Specific heat BTU/ lbm-0 F See Table 16

3. Thermal conductivity BTU/hr-ft-See Table 16 I

OF

L-2009-069 Attachment I Page 19 of 44 Item Parameter -Description Units Value Comments No.

4. Emissivity versus temperature See Table 16

L-2009-069 Page 20 of 44 Figure 1 PRESSURIZER LEVEL PROGRAM 100.0 80.0 C.

CL w

w C',

60.0 40.0 20.0 0.0 +-

506 522 538 554 570 586 VESSEL AVERAGE TEMPERATURE, TAVE (F) 602

o

~3.

TOTAL PR4IMARY COOLANT FLOV SzI CL Ii.

0

.*0.0 1.0

?--0 3.0 4.0 5.0

'6.0 7,0 8.0 9,O 10.0

~TIME.

SEC Figure 15.2.5-1 St. Lucie Unit 1 -Power.

Heat Flux and Flow

-Loss Of C;oolant Flow CDC

~

L-2009-069 Attachment I Page 22 of 44 Figure 3 - Location of Fuel Rods and Guide Tubes in Fuel Assemblies t

CORE REACTOR EQUIVALENT

/f

~

/VESSEL 13W

I I" 1 1 I

0

L-2009-069 Page 23 of 44 Figure 4 - Location of Fuel Assemblies in the Core 6

W V

P NM L K H 0 F

E D

SIII II M42 AA4IE AE O I MD IV-6 J-I3 D-8 T-171 -

AAS2 a A47 BBOI OCCI BB4fcs84 A4 I

M4T1 E-S4-

-4 FEED D-4 IFEED T-4 N-3 1-5 I*20

(

AA35 3-5 AA68 AA13 CC12 C35 820 C609 8B8 CC43 CC1 AAI [M2 R-18 R-13 FEWD FEED X-13 FEED 8-13 FEED FEED G-13 0.7 1

AA65 CC-1 CC40 889 830 8846 BB2 8839 B822 BB11 C056 CC2 AA76 G-18 FEED FEED

"-3 0-13 0C19 L-15 R-19 V-13 F-3 FEED FEED 0-15 FAA2 0057 8825 B855 CC34 M 065 M63 ZCC38 8848 883 CC5I Mr AA4:

M-15 FEED F-6 1-15. FEED 84 FEED F-9 FEED E-15 S-6 FEED J-5 F-6 270 LI A

c CCS B

38 CU' 2

2 0BB 024 AA2'" C48 87 BB1 CC6 AA31 FEED C-16 E-17 FEED 8-7 FEED L-5 FEED X-7 FEED C-17 W-18 FEED W-9 8849 CC49 8821 OC42 MS AAo AM2 cc47 M MC 4

M14 W

8833 A04 8802 O.9

-5 FEED N-4 FEED G-2 L-20 8-Il FEED W651 8-11 E-2 FEED J-4 FEED 21 A7

'-5 CEC 887 OW43 AA71 C2 AA24 CC30 8,5I CC3M AA22 OC21 AA70 B53 BBI- 008 s-i8 M FEED N-28 W-7

-06 FEED W-S FEED R-I5 FEED L-%5 FEED N.I6 C-7 J-28 FEED

-18 883 CC70 8858 CC41 BB31 CC40 8863 S51 B845 CC62 8824 0CMO 8841 C71 883 2ý k39 DBI FEEDI R-11 FEED E-11 FEED B-9 7 0-15 FEED T-11 FEED 0G-1 FEED V-4

-13 CC15 B5 54 MAA75 032 AA23 CC23 8888 CC28 AA28 CC29 AA64 83i7 BB17 C016 S-4 kO FEED N-2 WV-15 J-6 FEED L-6 FEED 0-7 FEED W

-I9 FEED N46 C-S5 J-2 FEVD -A

- 841 C84 54 823 CC65 AA5 AA18 A25 CC53 AA26 AA17 AAM 8850 8026 0059 B894 E-17 D-17 FEED N-1I FEED 02 X-11 C-Il FEED F-11 L-2 R-20 FEED J-18 FEED V-17 AA32 CC13I B14 8842

G39 MS 00:BB28 8

CM2M 0084 85B8 B813 CC14 AA55

_-13 FEED C-6 R-6 FEED 8-t5 FEED L-17 FEED X-15 FEED G-5 W-8 FEED W-13 AAM50 CCA37 89 BB5 CC44 AA73 CC.8 AAMI 0C47 B8586 854 001 MAS MA41 S-7 N-7 FEED F-46 T-7, FEED 8-13 FEED F-I3 FEED E-7 9-16 FEJD 4-7 F-I V.72 C03 C036 B812 BB29 BB64 BB57 BB50 88]32 88I8 CC6i 07 4 M47 V-7 FEED FEED 819 0-9 0-3 L-7 R-S V-S F-i9 FEED FEED R,4 19

-18

-17

-14

-- 13

-12

-- 11

-10

-4 AA691 AM I CGS CC361 815 10072 B88 0C5816 CCIl M AA67 V-15

-9 M

FEED FEED ko9 FEED B-9 FEED FEED G-9 0-4 FwromCyde 14 Z-ZY Av~mbyr defi~er

[jPrevious Cycle WRofl AMI1AM3 1-8 J 4-15 885 005 j 881 CC"? 881 M33P444 2_________

B" MA/57 PA34T$iM8 L

E-V-IS 180° Florida Power & Light Company St. Lucie Plant Unit 1 St. Lucie Unit 1, Cycle 21 Core Loading Pattern Figure 4.3-45A Amendment No. 22 (05/07)

L-2009-069 Attachment I Page 24 of 44 Table 1 Volume vs. Height for the Reactor Vessel with Internals Installed.

Region Elevation Volume vs. Height Volume

( fi )

( ft3 per ft)

(ft 3 )

UGS support plate to top of vessel 6.6 699 (Region V6)

FAP to UGS support plate (Region 10.6 114.2 1210 V5)

Core Region (Fuel Alignment Plate (FAP) to CSP) (Regions V2, V3 &

12.8 69.7 892 V 4 )

CSB to vessel annulus (Region V1, 29.7 35 1039.5 Annulus)

Bottom of vessel to Core Support Plate (CSP) (Region V1, Lower 10 950.5 Plenum)

Sources.: Ref. 1, Tables 4.4-4B, 4.4-4C and Figure 4.4-21.

L-2009-069 Attachment I Page 25 of 44 Table 2 Component Data Required Component Flow Diagram.

Component Information Pressurizer PORVs V1402 8770-G-078 Sheet 1 A, Rev 30 8770-9676 Rev 1 V 1404 8770-9677 Rev 2 8770-9678 Rev 1 8770-9679 Rev 2 8770-9680 Rev 4 8770-9681 Rev 7 8770-9682 Rev 2 8770-9683 Rev I Pressurizer Safety Valves V1200 8770-G-078 Sheet 1 A, Rev 30 8770-13730, Rev I V1201 8770-13731, Rev I V1202 Main Steam Safety Valves V8201 8770-G-079, Sheet 1, Rev. 53 8770-993, Rev 4 V8202 8770-990, Rev 9 V8203 V8204 V8205 V8206 V8207 V8208 V8209 V8210 V8211 V8212 V8213 V8214 V8215 V8216 Atmospheric Dump Valves HCV-08-2A 8770-G-079, Sheet 1, Rev. 53 8770-12944, Rev I HCV-08-2B 8770-8971, Rev I Turbine Control Valves (Governor)

FC-8-4 I

70G0*

he

,Rv 587-13 e

FCV-08-644 I 8770-G-079, Sheet 2, Rev. 45 1 8770-103, Rev 7

L-2009-069 Attachment I Page 26 of 44 Component Flow Diagram Component Information FCV-08-645 8770-115, Rev 11 FCV-08-646 8770-116, Rev 24 FCV-08-647 Turbine By-Pass Valves PCV-8801 8770-G-079, Sheet 2, Rev. 45 8770-2082, Rev 10 PCV-8802 8770-2083, Rev 11 PCV-8803 PCV-8804 PCV-8805 Turbine Stop Valves (Throttle)

FCV-08-640 8770-G-079, Sheet 2, Rev. 45 8770-103, Rev 7 FCV-08-641 8770-115, Rev 1I FCV-08-642 8770-116, Rev 24 FCV-08-643 Main Feed Isolation Valves HCV-09-7 8770-G-080, Sheet 3, Rev 54 8770-14210, Rev 0 HCV-09-8 8770-14211, Rev 0 Main Steam Isolation Valves HCV-08-IA 8770-G-079, Sheet 1, Rev. 53 8770-9673, Rev 10 HCV 1 B I

Main Steam Check Valves V08117 8770-G-079, Sheet 1, Rev. 53 8770-8950, Rev 4 V08148 8770-8951, Rev 2 8770-8952, Rev 0 8770-9673, Rev 10 8770-9674, Rev 8 Miscellaneous Components V2526 V2501 V2118 V2623 V2500 V2101 V2322 SS (Suction Stabilizer for Charging Pump IC)

SS-02-IC CHG PP IC (Charging Pump IC)

PD (Pulsation 8770-G-078 Sheet 121A Rev. 38 8770-1380, Rev. 7 8770-1589, Rev. 9 8770-2699, Rev 2 8770-853, Rev 1 8770-1589, Rev 9 8770-1592 Rev. 10 8770-9301 Rev. 1 8770-9302 Rev. 5 8770-G-078 Sheet 120B Rev 17 8770-205 Rev. 0 8770-364 Rev. 4 8770-12137 Rev.

8770-12138 Rev.

8770-9982 Rev. 1 5

0

L-2009-069 Attachment I Page 27 of 44 Component Flow Diagram Component Information Damper on CHG PP I C)

V02134 V2336 FE-2212 V2429 V2430 MV-02-2 Regen HT EXCH (Regenerative Heat Exchanger)

V2319 SS 1 B SS (Suction Stabilizer for Charging Pump I B)

CHG PP lB (Charging Pump I B)

PD (Pulsation Damper on CHG PP I B)

V02133 V2337 V2316 SS-02-1A SS (Suction Stabilizer for Charging Pump IA)

CHG PP IA (Charging Pump I A)

PD (Pulsation Damper on CHG PP IA)

V2339 8770-9981 Rev. 1 8770-14099 Rev. 1 8770-14084 Rev. 1 8770-14345 Rev. 1 8770-9379 Rev. 1 8770-23 10 Rev. 0 8770-1588 Rev. 5 8770-1571 Rev. 8 8770-10468 Rev. 0 8770-420 Rev. 2 8770-1592 Rev. 10 8770-9301 Rev. I 8770-9302 Rev. 5 8770-12137 Rev. 5 8770-205 Rev. 0 8770-364 Rev. 4 8770-12138 Rev. 0 8770-9982 Rev. I 8770-9981 Rev. I 8770-14084 Rev. 1 8770-14099 Rev. 1 8770-14345 Rev. 1 8770-9379 Rev. 1 8770-1592 Rev. 10 8770-9301 Rev. I 8770-9302 Rev. 5 8770-12137 Rev. 5 8770-364 Rev. 4 8770-12138 Rev. 0 8770-205 Rev. 0 8770-14345 Rev. I 8770-9378 Rev. 0 8770-10883 Rev. 2 V02132

L-2009-069 Page 28 of 44 Component Flow Diagram Component Information V2338 SE-02-2 V2433 SE-02-1 V2432 V2519 V2515 V2516 V2341 LCV-2110P V2342 LTDN (Letdown Heat Exchanger)

V2347 PCV-2201Q V2349 FE-2202 V2358 Purif FLTR IA (Purification Filter 1A)

V2360 V2520 V2369 V2370 V2378 V2382 V2395 S2900 V2415 V2418 Purif FLTR 1B (Purification 8770-1588 Rev. 5 8770-12507 Rev. 0 8770-12508 Rev. 0 2998-19678 Rev. 0 2998-19677 Rev. 0 8770-14084 Rev. 1 8770-14099 Rev. 1 8770-12507 Rev. 0 8770-12508 Rev. 0 2998-19677 Rev. 0 8770-1570 Rev. 10 8770-926 Rev. 13 8770-858 Rev. 2 8770-928 Rev. 8 8770-860 Rev. 4 8770-928 Rev. 8 8770-860 Rev. 4 8770-1588 Rev. 5 8770-16166 Rev. 0 8770-787 Rev. 4 8770-1588 Rev. 5 8770-419 Rev. 2 8770-G-078 Sheet 120A Rev. 023 8770-1578 Rev. 4 8770-971 Rev. 9 8770-1591 Rev. 5 8770-2301 Rev. 1 8770-1592 Rev. 10 8770-14147 Rev. 1 8770-558 Rev. 3 8770-8852 Rev. 2 8770-8617 Rev. 3 8770-1592 Rev. 10 8770-853 Rev. 1 8770-1592 Rev. 10 8770-1589 Rev. 9 8770-1592 Rev. 10 8770-1592 Rev. 10 8770-1592 Rev. 10 8770-1480 Rev. 1 8770-1592 Rev. 10 8770-1592 Rev. 10 8770-14147 Rev. 1 8770-558 Rev. 3 8770-8852 Rev. 2

L-2009-069 Attachment I Page 29 of 44 Component Flow Diagram Component Information Filter IB)

V2452 FE-8011 FE-8021 V09252 V09294 AFW PP IA AFW PP lB AFW PP iC V09139 V09140 FE-09-2C MV-09-11 MV-09-12 V09151 V09157 V09152 V09158 V09123 V09107 V09108 V09124 FE-09-2A FE-09-2B MV-09-9 MV-09-10 V09119 V09135 V09120 V09136 V1403 V 1405 V1406 V1407.

PZR Quench Tank V1252 V1253 PCV-II OOE PCV-II OOF V1248 V1249 8770-G-079, Sheet 1, Rev. 53 8770-G-080, Sheet 3, Rev 54 8770-G-080, Sheet 4, Rev. 41 8770-G-078 Sheet I 1A, Rev 30 8770-8617 Rev. 3 8770-1592 Rev. 10 8770-965, Rev 5 8770-965, Rev 5 8770-5736, Rev 4 8770-7139, Rev 3 8770-3044, Rev 3 8770-4409, Rev 0 8770-15879, Rev 0 8770-3183, Rev 7 8770-4408, Rev 0 8770-1398, Rev 6 8770-1257, Rev 3 8770-3544, Rev 0 8770-3294, Rev 4 8770-6967, Rev 5 8770-6967, Rev 5 8770-3775, Rev 6 8770-3775, Rev 6 8770-3774, Rev 3 8770-125 1, Rev 2 2998-20110, Rev 1 8770-3775, Rev 6 8770-1251, Rev 2 8770-1251, Rev 2 8770-3294, Rev 4 8770-3544, Rev 0 8770-6966, Rev 5 8770-6966, Rev 5 8770-3775, Rev 6 8770-3775, Rev 6 8770-3774, Rev 3 8770-1251, Rev 2 8770-1374, Rev 10 8770-1374, Rev 10 8770-1750, Rev 5 8770-1750, Rev 5 8770-898, Rev 3 8770-1769, Rev 4 8770-1769, Rev 4 8770-864, Rev 2 8770-970, Rev 15 8770-6586, Rev 3 8770-6777, Rev 1 8770-16184, Rev 0

L-2009-069 Attachment I Page 30 of 44 Component Flow Diagram Component Information V1250 8770-1769, Rev 4 8770-16184, Rev 0 8770-1769, Rev 4 V1251 SO-03-13 SO-03-14 SO-03-15 V3427 V3405 V3414 V3654 V3656 IICV-3616 FICV-3626 I-ICV-3636 HCV-3646 V3113 V3123 V3133 V3143 FE-3311 FE-3321 FE-3331 FE-3341 HCV-3615 HCV-3625 HCV-3635 1HCV-3645 V3114 V3124 V3134 V3144 FE-3312 FE-3322 FE-3332 FE-3342 HCV-3617 FICV-3627 HCV-3637 HCV-3647 V3106 V3107 V3206 V3207 FCV-3306 FE-3306 8770-G-078 Sheet 130A, Rev 27 8770-G-078 Sheet 131A, Rev 27 8770-G-078 Sheet 130B, Rev 31 8770-1768, Rev 8 8770-1768, Rev 8 8770-1768, Rev 8 8770-1377, Rev 6 8770-1377, Rev 6 8770-1376, Rev 5 8770-1376, Rev 5 8770-1376, Rev 5 8770-1376, Rev 5 8770-12709, Rev 10 8770-1570, Rev 10 8770-1570, Rev 10 8770-1570, Rev 10 8770-1375, Rev 6 8770-1375, Rev 6 8770-1375, Rev 6 8770-1375, Rev 6 8770-1748, Rev 7 8770-1748, Rev 7 8770-1748, Rev 7 8770-1748, Rev 7 8770-2301, Rev 1 8770-2301, Rev 1 8770-2301, Rev 1 8770-2301, Rev 1 8770-1376, Rev 5 8770-1376, Rev 5 8770-1376, Rev 5 8770-1376, Rev 5 8770-3646, Rev 1 8770-3646, Rev 1 8770-9348, Rev 3 8770-9348, Rev 3 8770-861, Rev 2 8770-930, Rev 8 8770-2301, Rev I I

1.

L-2009-069 Attachment I Page 31 of 44 Table 3 Secondary Side Volume per Unit Height ( ft3 ft) 51.552 49.947

-41.677 40.344 39.240 35.000

-32.583

30. 191 283.83"3

--28.125

-25.573

-22.271 18.802 15.333 12.865 8.396 4.927 2.0 0

HT ABOVE T/5 SEC. rACE (FT)

T 4.679 -

178.960 4.679 178.950

-239. 1 67.227

-52.285 10.178

-282.671 37.679

- 210.601 97.753 70.432 70.432 70.432 70.432 70.432 69.829 70.345

- -282.671 276.779

-277.828

-164.980

-227.047

-150.038 80.610 80.610 80.610 80,610 80.610 80.007 80.523 00WN~CNER RI 5~

TOTAL DOWNCOMER RISER TOTAL

L-2009-069 Attachment I Page 32 of 44 Table 4 Spacer Grid Locations Grid #

Distance (in) 1 6.302 2

18.185 3

36.797 4

55.656 5

74.515 6

93.374 7

112.233 8

131.092 9

148.272 Notes: Measured from bottom of fuel assembly to top of grid.

L-2009-069 Page 33 of 44 Table 5 - Single Phase Homologous Head and Torque Curves CURVE 1 CURVE 2 CURVE3 CURVE4 CURVE5 CURVE6 CURVE 7 CURVE8 HAN Head HVN Head HAD Head HVD Head HAT Head HVT Head HAR Head Curve Curve Curve Curve Curve Curve Curve HVR Head Curve 0.0 1.580 0.0

-1.420

-1.0 3.150

-1.0 3.150 0.0 0.433 0.0 1.220

-1.0

-3.100

-1.0

-3.100 0.1 1.500 0.1

-1.215

-0.9 2.930

-0.9 2.810 0.1 0.474 0.1 1.182

-0.9

-2.550

-0.9

-3.010 0.2 1.420 0.2

-1.082

-0.8 2.700

-0.8 2.490 0.2 0.502 0.2 1.140

-0.8

-2.050

-0.8

-2.930 0.3 1.370 0.3

-0.912

-0.7 2.470

-0.7 2.180 0.3 0.512 0.3 1.085

-0.7

-1.600

-0.7

-2.810 0.4 1.330 0.4

-0.728

-0.6 2.300

-0.6 1.930 0.4 0.524 0.4 1.045

-0.6

-1.035

-0.6

-2.690 0.5 1.295 0.5

-0.494

-0.5 2.130

-0.5 1.720 0.5 0.546 0.5 1.000

-0.5

-0.830

-0.5

-2.520 0.6 1.270 0.6 0.000

-0.4 2.000

-0.4 1.550 0.6 0.583 0.6 0.950

-0.4

-0.513

-0.4

-2.340 0.7 1.240 0.7 0.208

-0.3 1.870

-0.3 1.440 0.7 0.641 0.7 0.900

-0.3

-0.246

-0.3

-2.150 0.8 1.182 0.8 0.435

-0.2 1.760

-0.2 1.345 0.8 0.712 0.8 0.870

-0.2 0.0112

-0.2

-1.960 0.9 1.105 0.9 0.708

-0.1 1.660

-0.1 1.285 0.9 0.800 0.9 0.865

-0.1 0.343

-0.1

-1.715 1.0 1.000 1.0 1.000 0.0 1.580 0.0 1.220 1.0 0.908 1.0 0.908 0.0 0.433 0.0

-1.420 CURVE9 CURVE 10 CURVE 11 CURVE 12 CURVE 13 CURVE 14 CURVE 15 CURVE 16 BAN Torque BVN Torque BAD Torque BVD Torque BAT Torque BVT Torque BAR Torque Curve Curve Curve Curve Curve Curve Curve BVR Torque Curve 0.0 0.770 0.0

-1.450

-1.0 2.290

-1.0 2.290 0.0

-1.440 0.0 1.315

-1.0

-5.030

-1.0

-5.030 0.1 0.802 0.1

-1.112

-0.9 2.040

-0.9 2.120 0.1

-0.920 0.1 1.245

-0.9

-4.540

-0.9

-4.610 0.2 0.845 0.2

-0.872

-0.8 1.785

-0.8 1.960 0.2

-0.630 0.2 1.180

-0.8

-4.050

-0.8

-4.230 0.3 0.866 0.3

-0.648

-0.7 1.580

-0.7 1.830 0.3

-0.420 0.3 1.110

-0.7

-3.600

-0.7

-3.840 0.4 0.885 0.4

-0.442

-0.6 1.390

-0.6 1.720 0.4

-0.250 0.4 1.042

-0.6

-3.240

-0.6

-3.490 0.5 0.910 0.5

-0.270

-0.5 1.235

-0.5 1.640 0.5

-0.100 0.5 0.975

-0.5

-2.830

-0.5

-3.150 0.6 0.930 0.6 0.260

-0.4 1.090

-0.4 1.580 0.6 0.020 0.6 0.905

-0.4

-2.490

-0.4

-2.850 0.7 0.953 0.7 0.430

-0.3 0.980

-0.3 1.510 0.7 0.130 0.7 0.817

-0.3

-2.190

-0.3

-2.520 0.8 0.973 0.8 0.613

-0.2 0.880

-0.2 1.450 0.8 0.251 0.8 0.728

-0.2

-1.910

-0.2

-2.200 0.9 0.989 0.9 0.800

-0.1 0.810

-0.1 1.380 0.9 0.390 0.9 0.628

-0.1

-1.660

-0.1

-1.850 1.0 1.000 1.0 1.000 0.0 0.770 0.0 1.315 1.0 0.562 1.0 0.562 0.0

-1.440 0.0

-1.450

L-2009-069 Page 34 of 44 Table 6 Unit 1 Piping Isometric Drawings by P&ID Flow Diagram Isometric/Component Drawing Reactor Vessel 8770-G-078, Sheet 1 OB, Rev. 26 8770-44, Rev 5 8770-8862, Rev 0 8770-8863, Rev 0 8770-8864, Rev 0 8770-8865, Rev 0 8770-8873, Rev 1 8770-8874, Rev 0 8770-8877, Rev 0 8770-15672, Rev 0 8770-15673, Rev 0 Primary Loop Piping (RCS) 8770-G-078, Sheet I 1OB, Rev. 26 8770-39, Rev 3 8770-40, Rev 3 8770-530, Rev 3 8770-78 1, Rev 3 8770-880, Rev 1 8770-1496, Rev 2 Reactor Coolant Pumps 8770-G-078, Sheet l I lA, Rev. 15 8770-15, Rev 8 8770-G-078, Sheet II IB, Rev. 15 8770-178, Rev 11 8770-G-078, Sheet 11 IC, Rev. 14 8770-54, Rev 9 8770-G-078, Sheet I ID, Rev. 16 Steam Generators 8770-G-078, Sheet I IOB, Rev. 26 8770-13348, Rev 1 8770-G-080, Sheet 3, Rev. 54 8770-G-079, Sheet 1, Rev. 53 Pressurizer/Surge Line/Spray Lines/Relief Lines 8770-G-078, Sheet I 1A, Rev. 30 8770-G-125 Sheet RC-AB-I, Rev 3 8770-15377, Rev 0 8770-15287, Rev 0 8770-15307, Rev 0 8770-16184, Rev 0 8770-1658, Rev 0 8770-15820, Rev 0 8770-6624, Rev 2 8770-15298, Rev 0 8770-15819, Rev 0 8770-B-124 Sheet RC-187, Rev I

L-2009-069 Attachment I Page 35 of 44 Main Steam Lines Out to the Turbine Stop Valves 8770-G-079, Sheet 1, Rev. 53 8770-G-125, Sheet MS-L-1, Rev 6 8770-G-079, Sheet 2, Rev. 45 8770-G-125, Sheet MS-L-6, Rev 6 Main Feedwater Lines from the Isolation Valves to the Steam Generator Inlet 8770-G-080, Sheet 3, Rev. 54 8770-G-125, Sheet BF-M-06, Rev 4 Auxiliary Feedwater Lines 8770-G-080, Sheet 4, Rev. 41 8770-G-125, Sheet BF-M-07, Rev 6 18770-G-125, Sheet BF-M-08, Rev 10 Safety Injection 8770-G-078, Sheet 130A, Rev. 27 8770-G-125, Sheet SI-N-5, Rev 2 8770-G-078, Sheet 130B, Rev. 31 8770-G-125, Sheet SI-N-6, Rev 4 8770-G-078, Sheet 131A, Rev. 27 8770-G-125, Sheet SI-N-7, Rev 3 8770-G-078, Sheet 131B, Rev. 19 8770-G-125, Sheet SI-N-8, Rev 4 8770-G-125, Sheet SI-N-10, Rev 3 8770-G-125, Sheet SI-N-12, Rev 2 8770-B-124 Sheet SI-27 Rev 13 8770-B-124 Sheet SI-28 Rev 12 8770-B-124 Sheet SI-29 Rev 12 8770-B-124 Sheet SI-30 Rev 11 8770-B-124 Sheet SI-31 Rev 13 8770-B-124 Sheet SI-32 Rev 9 8770-B-124 Sheet SI-33 Rev 14 8770-B-124 Sheet SI-34 Rev 10 8770-B-124 Sheet SI-128 Rev 1 8770-B-124 Sheet SI-129 Rev 3 8770-B-124 Sheet SI-130 Rev 4 8770-B-124 Sheet SI-131 Rev 2 Charging and Letdown System (CVCS) 8770-G-078, Sheet I IOB, Rev. 26 8770-G-078, Sheet 120A, Rev. 23 87.70-G-078, Sheet 120B, Rev. 17 8770-G-078, Sheet 121A, Rev. 38 8770-G-078, Sheet 121B, Rev. 32 8770-G-088, Sheet 1, Rev. 51 8770-G-125 Sheet CH-G-1 Rev. 2 8770-G-125 Sheet CH-G-2 Rev 1 8770-G-125 Sheet CH-G-3 Rev 4 8770-G-125 Sheet CH-G-4 Rev 0 8770-G-125 Sheet CH-G-5 Rev 0 8770-6-125 Sheet CH-G-8 Rev 2 8770-G-125 Sheet CH-G-9 Rev 4 8770-G-125 Sheet CH-G-12 Rev 6 8770-G-125 Sheet CH-G-13 Rev I 8770-B-124 Sheet CH-1 Rev 2 8770-B-124 Sheet CH-2 Rev 2 8770-B-124 Sheet CH-3 Rev 3 8770-B-124 Sheet CH-4 Rev 4 8770-B-124 Sheet CH-37 Rev 2

L-2009-069 Attachment I Page 36 of 44 8770-B-124 Sheet CH-43 Rev 5 8770-B-124 Sheet CH-63 Rev 7 8770-B-124 Sheet CH-64 Rev 5 8770-B-124 Sheet CH-65 Rev 12 8770-B-124 Sheet CH-66 Rev 9 8770-B-124 Sheet CH-68 Rev 10 8770-B-124 Sheet CH-69 Rev 8 8770-B-124 Sheet CH-70 Rev 7 8770-B-124 Sheet CH-71 Rev 6 8770-B-124 Sheet CH-72 Rev 8 8770-B-124 Sheet CH-74 Rev 12 8770-B-124 Sheet CH-75 Rev 7 8770-B-124 Sheet CH-77 Rev 10 8770-B-124 Sheet CH-78 Rev 5 8770-B-124 Sheet CH-79 Rev 8 8770-B-124 Sheet CH-80 Rev 14 8770-B-124 Sheet CH-82 Rev 21 8770-B-124 Sheet CH-92 Rev 11 8770-B-124 Sheet CH-124 Rev 11 8770-B-124 Sheet CH-125 Rev 7 8770-B-124 Sheet CH-126 Rev 8 8770-B-124 Sheet CH-128 Rev 5 8770-B-124 Sheet CH-129 Rev 8 8770-B-124 Sheet CH-130 Rev 6 8770-B-124 Sheet CH-141 Rev 11I 8770-B-124 Sheet CH-142 Rev 7 8770-B-124 Sheet CH-143-1 Rev 2 8770-B-124 Sheet CH-143-2 Rev 6 8770-B-124 Sheet CH-178 Rev 4 8770-B-124 Sheet CH-187 Rev I 8770-B-124 Sheet CH-188 Rev 0 8770-B-124 Sheet CH-189 Rev 0 8770-B-124 Sheet CH-193 Rev 2 8770-B-124 Sheet CH-232 Rev 0 8770-B-124 Sheet CH-264 Rev 0 8770-B-124 Sheet RC-1 Rev 6 8770-B-124 Sheet RC-2 Rev 7 8770-B-124 Sheet RC-3 Rev 6 8770-B-124 Sheet RC-4 Rev 5 8770-B-124 Sheet RC-6 Rev 1

L-2009-069 Page 37 of 44 Table 7. TEMPERATURE vs. DOPPLER REACTIVITY WORTH Current Analysis Value EPU Analysis Value FUEL TEMPERATURE DOPPLER REACTIVITY FUEL TEMPERATURE DOPPLER REACTIVITY (OF)

(Ap)

(OF)

(Ap) 0.0 0.0*

250.0 0.0 400.0

-0.0037338 667.5

-0.0098574 808.1

-0.0128639 946.5

-0.0186432 No changes from current No changes from current

94.

00542 analysis analysis 1077.9

-0.0181490 1199.1

-0.0203649 1309.0

-0.0222887 1445.5

-0.0246159 5000.0

-0.0246159**

Notes:

assumed/extrapolated to be the same as the next value.

assumed/extrapolated to be the same as the previous value.

Table 8. CHANGE IN REACTIVITY vs. MODERATOR DENSITY Current Analysis Value EPU Analysis Value CHANGE IN MODERATOR CHANGE IN MODERATOR REACTIVITY (Ap)

DENSITY (Ibm/ft3)

REACTIVITY (Ap)

DENSITY (Ibm/ft3)

-0.350 0.0 No changes from current No changes from current

-0.270 2.1 analysis analysis

-0.190 5.0

-0.100 10.0

-0.090 12.1

-0.060 15.0

-0.030 20.0

-0.020 22.1

-0.012 25.0

-0.005 30.0

-0.0001 32.1

-0.0000 35.0

+0.0020 36.7 0.0 40.0 0.0 43.0 0.0 45.0 0.0 1.0x10 6 Note: ***

Reactivity corresponding to the most positive MTC @ HFP, BOC

L-2009-069 Attachment I Page 38 of 44 Table 9. RCS TEMPERATURE vs. MODERATOR REACTIVITY Current Analysis Value EPU Analysis Value RCS MODERATOR RCS MODERATOR TEMPERATURE (0F)

REACTIVITY (Ap)

TEMPERATURE (*F)

REACTIVITY (Ap) 68.0 0.06345*

300.0 0.06345 No changes from No changes from 450.0 0.03959 current analysis.

current analysis.

532.0 0.01627 572.0**

0.0000"*

Notes:

Assumed/extrapolated to be the same as the next value.

Assumed to the nominal temperature at which the MTC would be equal to 0.0.

Table 10. AXIAL HEIGHT vs. AXIAL POWER SHAPE Current Analysis Value EPU Analysis Value (WEC)

(FPL)

AXIAL HEIGHT Axial Power Shape AXIAL HEIGHT Axial Power Shape (ft)......

~(*)

f)...

2.2783 0.38000 2.278 0.81301 4.5566 0.710 4.556 0.92260 6.8349 1.370 6.834 1.00900 9.1132 1.635 9.112 1.21700 11.3917 1.020 11.390 1.04567 Notes:

FPL can not confirm the current values provided by Westinghouse for the Axial Power Shape data. FPL has provided values for the EPU from the current LOCA Containment Re-Analysis.

Axial height from the bottom of core.

L-2009-069 Attachment I Page 39 of 44 Table 11 - PSL Unit-1 RPS, ESFAS and AFAS Setpoints and Safety Analysis Limits Functional Description Monthly Tech Spec Setpoint Current Setpoint or EPU Setpoint or Comments Surveillance Uncertainty Req.

Uncertainty Setpoint (current cycle)

Requirement RPS PZR Press Hi 2397.5 psia

< 2400 psia

+/- 22 psi (Normal)

+/- 40 psi (Normal)

Current cycle safety analysis parameter document

+/-- 80 psi (Accident)

+/- 80 psi (Accident) includes a target analysis value of+ 40 psi (Normal)

RPS Cont. Press Hi 3.175 psig

3.3 psig

+/- 1.3 psi

+/- 1.3 psi RPS S/G Press Lo 626.1 psia

> 600 psia

+/- 32 psi (Normal)

+/- 40 psi (Normal)

Current cycle safety analysis parameter document

+/- 80 psi (Worst Normal) includes target analysis value of +/- 80 psi (Worst Normal). Worst Normal defined as Containment Temperature > 1 1 IF but < 2000F.

RPS S/G Level Lo 21.0%

> 20.5%

+/- 3% (Normal)

+/- 5% (Normal)

Current cycle safety analysis parameter document

+/- 14% (Accident)

+/- 14% (Accident) includes a target analysis value of +/- 5% (Normal)

RPS RCS Low Flow

> 95% Design Flow 3.5%

4%

SIAS/CIS Cont. Press Hi 4.375 psig

< 5.0 psig

+/- 1.3 psi

+/- 1.3 psi CSAS Cont. Press Hi-Hi 9.375 psig

< 10.0 psig

+/- 1.3 psi

+/- 1.3 psi SIAS PZR Press Lo 1612.5 psia

> 1600 psia

+/- 22 psi (Normal)

+/- 40 psi (Normal)

+/- 80 psi (Accident)

MSIS S/G Press Lo 600 psig

> 585 psig

+/- 32 psi (Normal)

+/- 40 psi (Normal)

Current cycle safety analysis parameter document

+/- 80 psi (Worst Normal) includes a target analysis value of+/- 80 psi (Worst Normal). Worst Normal is defined as Containment Temperature > 11 F but < 2000F.

RAS RWT Level Lo 48 inches 48 inches

+/- 6 inches

+/- 6 inches AFAS S/G Level Lo 19.5%

> 19.0%

+/- 3% (Normal)

+/- 5% (Normal)

Current cycle safety analysis parameter document

+/- 14% (Accident)

+/- 14% (Accident) includes a target analysis value of+/- 5% (Normal)

AFAS S/G Press DP Hi 270 psid

< 275 psid Not specified

+/- 64 psi (Normal)

Worst Normal is defined as Containment

+/- 160 psi (Worst Normal)

Temperature > 11 IOF but < 2000F.

AFAS FW Press DP Hi 142.5 psid

< 150.0 psid Not specified

< 245 psid (setpoint)

AFAS logic time delay 235 sec 170 sec 170 sec (minimum act. time)

PORV Open Pressure N/A 2400 psia (nominal) 2400 psia (nominal)

For non-LTOP conditions, PORVs operate on RPS (setpoint)

PZR Press Hi Main Steam Safety RV N/A 1000 psia (nominal)

+ 1%, - 3% (tolerance) 3% (tolerance)

Current cycle safety analysis parameter document 1040 psia (nominal) 3% (accumulation) 3% (accumulation) includes a target analysis value of+/- 3% (tolerance)

PZR Safety RV N/A 2500 psia (nominal)

+ 3%, - 2.5% (tolerance)

+ 3%, - 2.5% (tolerance) 1 3% (accumulation) 3% (accumulation)

Note: When revised, Safety Analysis limits are set equal to the Tech Spec setpoint plus or minus the defined uncertainty.

L-2009-069 Page 40 of 44 TABLE 12 ST. LUCIE UNIT 1 - HIGH PRESSURE SAFETY INJECTION PUMP DELIVERY FLOW/PUMP DEGRADED PUMP NON-DEGRADED PUMP NOMINAL MINIMUM NOMINAL MAXIMUM 4-LOOP 3-LOOP 4-LOOP 3-LOOP RCS 4-LOOP LOWVEST TOTAL MINIMUM RCS 4-LOOP HIGHEST TOTAL MAXIMUM PRESSURE TOTAL 3-LOOPS MIN ANALYSIS PRESSURE TOTAL 3-LOOPS MAX ANALYSIS (psia)

(gpm)

(psia)

(gpm)

(gpm) 15 647 479 615 455 15 704 563 740 592 315 555 411 527 390 324 617 493 648 518 615 442 327 420 311 633 514 412 540 432 815 346 256 329 244 839 432 346 455 364 1015 208 154 197 146 1045 329 263 351 281 1115 66 48 62 46 1148 261 209 286 229 1125 26 18 25 17 1158 254 203 279 223 1129 0

0 0

0 1162 250 200 276 221 1215 0

0 0

0 1251 168 134 200 160 1265 0

0 0

0 1303 89 72 138 110

L-2009-069 Attachment I Page 41 of 44 Table 13. ST. LUCIE UNIT 1 -

LOW PRESSURE SAFETY INJECTION PUMP DELIVERED FLOW I

Min Degraded LPSI Flow/Pump (4 Valves)

I Max LPSI Flow/Pump (4 Valves)

I RCS TOTAL 3-LOOP PRESSURE FLOW MINIMUM (PSIA)

(GPM)

(GPM) 144.44 0

0 144.42 61 45 144.29 161 119 143.22 461 340 141.54 711 525 138.92 961 709 134.83 1211 894 129.61 1461 1078 123.24 1712 1263 115.69 1962 1447 106.95 2212 1632 96.99 2463 1817 85.78 2713 2002 73.31 2964 2187 44.47 3466 2557 10.30 3968 2927 RCS TOTAL 3-LOOP PRESSURE FLOW MAXIMUM (PSIA)

(GPM)

(GPM) 202.48 0

0 202.46 56 43 202.34 156 119 201.30 456 348 199.65 706 540 197.01 956 731 192.68 1206 922 187.10 1456 1114 180.25 1706 1305 172.10 1957 1497 162.61 2207 1688 151.76 2458 1880 139.52 2708 2071 125.86 2959 2263 94.14 3461 2647 56.39 3963 3031 Max LPSI Flow with Two Pumps (4 Valves)

RCS TOTAL 3-LOOP PRESSURE FLOW MAXIMUM (PSIA)

(GPM)

(GPM) 202.48 0

0 202.41 111 85 201.96 311 238 198.03 911 697 191.81 1411 1079 182.62 1911 1462 169.77 2412 1844 153.70 2912 2227 134.38 3413 2610 111.78 3913 2993 85.86 4414 3376 56.60 4915 3759 23.96 5416 4143 17.02 5517 4219 Min Degraded LPSI Flow/Pump (2 Valves)

RCS TOTAL 1-LOOP PRESSURE FLOW MINIMUM (PSIA)

(GPM)

(GPM) 144.44 0

0 144.37 61 30 143.98 161 79 140.64 461 225 135.41 711 347 127.72 961 469 117.05 1211 591 103.73 1461 713 87.73 1712 835 69.04 1962 957 52.14 2162 1055 47.64 2212 1080 43.02 2262 1104 33.47 2363 1153 23.48 2463 1202 18.32 2513 1226 Each LPSl and HPSI provides injection flow to all four legs.

Failure of a Diesel Generator will take-1 LPSI with 2 Valves and 1 HPSI Off.

For Max with (LPSI and HPSI), Use (LPSI Max + HPSI Max)

For Min with (1 LPSI and 1 HPSI), Use Maximum of (Degraded Minimum LPSI, HPSI)

L-2009-069 Page 42 of 44 Table 14 Primary Loop Pressure Drop Distribution Geometry AP Geometry AP Friction Forward Reverse Flow Reference #

Station AP Flow EPU Values

( Pji(ii.

(psi);.*,.

SG Inlet to SG Outlet 39.9432 8.7779 11.8452 27 Assumed to be the Across RCP 72 / 80 N/A N/A same as current Pressure<

Current Values, drop (ps-i-)

SG Inlet to SG Outlet 28.0 / 28.5 N/A N/A 29 Across RCP 72 / 80 N/A N/A 29 Note: Values with slashes mean Loop B / Loop A.

Table 15 Heat Balance Information

% EPU Power Feedwater Flow Steam Flow Feedwater Turbine Inlet ibm/hr (2 SG) ibm/hr (2 SG)

Temperature, F Pressure, psia 100 13,303,150 13,236,690 436.2 751.4 90 11,834,340 11,767,890 427.0 664.6 75 9,666,014 9,599,566 410.5 538.4 50 6,199,094 6,132,645 375.3 337.5 25 2,972,477 2,905,988 323.7 173.4

L-2009-069 Attachment I Page 43 of 44 Table 16 RCS Pressure Boundary Material Property Data Material Density Specific Thermal Emissivity Comment (lbm/ft3 )

Heat Conductivity vs Temp (Btu/lbm-F)

(Btu/hr-ft-F)

Carbon 483.8

0.129*

22.92*

0.78-0.82

SA-516 Gr 70 Steel

@130-530

- smooth oxidized C**

iron Stainless 499.4*

0.13*

10.44*

0.57-0.66

304/304L SS Steel

@230-870

- 316 SS repeated C**

heating Inconel 528.8 0.106 8.58 0.85-0.98 600

@480-1090 C Inconel 511.5 0.107 7.75 0.85-0.98 Emissivity assumed 690

@480-1090 C same as Inconel 600

L-2009-069 Page 44 of 44 Appendix A - Calculation of Fuel Assembly Grid Weight and Surface Area AREVA GRID WEIGHT AND SURFACE AREA HTP Zirc-4 weight gins Ref 1.

1046 Zirc 4 density gm/cc Ref. 2, 3 6.6 vol cc 158.48 wt in pounds 2.306 453,592 gm/lb Strip thickness inches Ref 1.

0.017 Note 1.

Volume in3 9.671 Area in2 568.88 wetted area X2 1137.76 Wetted area sq ft 7.90 HMP Inconel 714 weight gms Ref 1.

976 Inconel density lb/in3 Ref 4, 0.296 Strip thickness inches Ref 1.

0.0125 Note 2.

wt in pounds 2.15 Volume in3 7.27 AREA in2 581.54 Wetted area X2 1163.09 Wetted area sq ft 8.08

Reference:

1. Areva Document 32-0979930-000 PSL-1 Cycle 22 2: Zirconium Associatiion Bulletin # 6, "General Data Covering Zirconium and Zirconium Alloys"

3. ATI Wah Chang,Technical Data Sheet Properties of Zircaloy-4

4. Special Metals Handbook Notes:

1. Assume that all 56 strips are the same thickness 0.017 in. (4 side strips 0.025 in thick)

2. Assume that all 56 strips are the same thickness 0.0125 in. (4 side strips 0.025 in thick)

Per Assembly Weight lbs Area ft2 HTP 18.45 63.2092 HMP 2.15 8.08 Total 20.60 71.2862 2-Sq2 /'

HTP HMP Grid wts Area.xis

L-2009-069 Page 1 of 49 ST. LUCIE UNIT 2 EPU Input Data Request to NRC for LOCA Model Item Parameter -Description Units Value Comments No.

1.

Plant Operating Conditions For rated power conditions 1la.

(Current):

1. Primary and Secondary Flow rates:

1.1. Core flow Unc: + 14,500 gpm and gpm 412,000 min flow is 335,000.

1.2. Main coolant pumps 97,500 (2A1) gpm 96,000 (2A2)

RCP Pump Test Data gpm 95,000 (213 1) 94,000 (2B2) 1.3. Steam flow Ibm/hr See Item I a 7.1 1.4. Feedwater flow Ibm/hr See Item Ia 7.1 1.5. SG recirculation ratio/boiler Power %Circ section flow Ratio Power-20 18.41 50 7.91

%CircRatio 70 5.42 90 3.96 100 3.46

2.

Primary and Secondary Pressures:

2.1. Pressurizer Nominal Operating psia 2250 Pressure is 2250 psia.

L-2009-069 Page 2 of 49 Item Parameter -Description Units Value Comments No.

Pressure range is 2225 to 2275, with Unc: +/- 45 Normal, + 90 Accident.

2.2. Core inlet Based on 2250 psia core psia 2286 outlet and 35.5 psi core pressure drop (UFSAR Table 4.4-4).

2.3. Core outlet Assumed to be the same as the pressurizer.

2.4. Reactor coolant pump Assume a I psi pressure discharge psia 2287 drop from RCP discharge to core inlet.

2.5. Steam generator dome SG outlet pressure from

psia 886.81 benchmark heat balance plus dP to upstream of flow restrictor 2.6. Turbine control valve inlet psia See Item la 7.3 2.7 Detailed primary loop Assumes 10% SG tube pressure drop distribution psi Table 13 below plugging.

3.

Primary and Secondary Temperatures:

3.1. Hot leg Assumed to be the same as the core outlet OF 600 temperature since the Rx vessel does not have Supper head injection.

3.2. Cold leg OF 549 Tcold temperature at full Unc: +/- 30F power.

3.3. Core outlet Based on Tcold of 549F and Tave of 574.5F.

L-2009-069 Page 3 of 49 Item Parameter -Description Units Value Comments No.

3.4. Upper Head Assumed to be the same as the core outlet OF 600 temperature since the Rx vessel does not have upper head injection.

4.

Water levels in the pressurizer and steam generators,

4. 1. Pressurizer

% Tap Span See Figure 1 4.2. Steam Generators in 411.3 Level above tubesheet

5.

Leakage flows (Bypass):

This is the total core

% of vessel 3.7 bypass maximum value flow for minimum core flow rate.

5. 1. Outlet nozzle clearances Assume bypass breakdown documented in Unit 1 UFSAR due to unit similarities.

5.2. Downcomer to upper head Assume bypass breakdown documented in Unit 1 UFSAR due to unit similarities.

5.3. CEA shrouds Equivalent to a fraction of the leakage through percent N/A guide tubes (item Ia.5.5.1). This has not been quantified.

5.4. Upper head to upper plenum (guide structure holes) percent N/A This has not been quantified.

5.5. Core bypass (guide tubes, barrel-baffle)

L-2009-069 Page 4 of 49 Item Parameter -Description Units Value Comments No.

5.5.1. Guide tubes Assume bypass breakdown documented in Unit 1 UFSAR due to unit similarities.

5.5.2. Barrel-baffle Assume bypass percent 0.47 breakdown documented

, in Unit 1 UFSAR due to unit similarities.

6.

Steam generator recirculation Power-ratio

%CircRatio Se-tmI-.

7. Heat balance information such as:

7.1. Feed and steam flows lbm/hr 11,905,010 Benchmark Heat 11,806,740 Balance 7.2. Feedwater temperature Benchmark Heat Balance 7.3. Turbine inlet pressure.

Benchmark Heat psia 852.7 Balance, Turbine Inlet Valve

1.

Plant Operating Conditions lb.

For EPU conditions.

1. Primary and Secondary Flow rates:

1.1. Core flow Minimum flow is gpm 412000 375,000 gpm.

1.2. Reactor coolant pumps 97,500 (2A1) gpm 96,000 (2A2)

RCP Pump Test Data gpm95,000 (2131) 94,000 (2B2) 1.3. Steam flow lbm!s See Item lb 7.1

L-2009-069 Page 5 of 49 Item Parameter -Description Units Value Comments No.

1.4. Feedwater flow Ibm/hr See Item lb 7.1 1.5. SG recirculation Power

%Circ ratio/boiler section flow Power-Ratio 25 13.86

%CircRatiocn 75 4.40 100 3.02

2.

Primary and Secondary u*

Pressures (absolute pressures):

.a:!f,*

5*

+:'

2.1. Pressurizer Range: 2225 to 2275 psia 2250 psia.

Unc.: _+ 45 psi normal,

+ 90 ps~i harsh.

2.2. Core inlet psia Assumed to remain 2286 similar to current conditions.

2.3. Core outlet psia Assumed to remain 2250 similar to current conditions.

2.4. Reactor coolant pump psia Assumed to remain discharge 2287 similar to current conditions.

2.5. Steam generator dome psia PRELIMINARY SG outlet pressure from Later895.8 heat balance plus dP to upstream of flow restrictor extrapolated using EPU flow Later 2.6. Turbine control valve inlet psia See Item lb.7:3 2.7 Detailed primary loop Assumes 10% SG tube pressure drop psi Table 13 below distribution plugging-

3.

Primary and Secondary 1*

L-2009-069 Page 6 of 49 Item Parameter -Description Units Value Comments No.

Temperatures:

3.1 Hot leg OF 606.0 Assumes 10% SG tube plugging.

3.2 Cold leg 551 Corresponds to 100%

OF Unc: +/- 3F Power. Tcold at zero power is 532F.

3.3 Core outlet Assumes 10% SG tube plugging.

3.4 Upper Head OF 606.0 Assumed to be the same as vessel outlet.

4 Water levels in the pressurizer i

and steam generators 4.1 Pressurizer

% Tap Span See Figure 1 below 4.2 Steam Generators in 411.3 Level above tubesheet 5

Leakage flows:

% of vessel 3.7 flow 5.1 Outlet nozzle clearances Assumed to be similar to current operating value.

5.2 DC to upper head percent 0.16 Assumed to be similar to current operating value.

5.3 CEA shrouds This has not been percent N/Aqanied quantified.

5.4 Upper head to upper plenum N/A This has not been (guide structure holes) percent quantified.

5.5 Core bypass (guide tubes, barrel-baffle)*i;*

5.5.1 Guide tubes pret1.6Assumed to be similar to current operating value.

5.5.2 Barrel-baffle pecn

.7Assumed to be similar to current* operating value.

6 Steam generator recirculation Power-ratio

%CircRatio

L-2009-069 Page 7 of 49 Item Parameter -Description Units Value Comments No.

7 Heat balance information such as:

7.1 Feedwater and steam flows lbm/hr See Table 14 7.2 Feedwater temperature OF See Table 14 7.3 Turbine inlet pressure.

psia See Table 14

2.

Analysis Topical Reports r

See References provided below applicable to rated power:

0 CENPD-132, through Suppl. 4-P-A, "Calculative Method for the CE Nuclear Power Large Break LOCA

1. Topical Report on the Evaluation Model",

licensing analysis of record See March 2001.

for LOCA at rated power and Comment See Comment 0

CENPD-137, through Suppl. 2-P-EPU conditions.

A, "Calculative Method for the ABB CE Small Break LOCA Evaluation Model",

"April 1998.

No new Topical Reports for EPU analyses.

Analysis results are in the UFSAR.

L-2009-069 Page 8 of 49 Item Parameter -Description Units Value Comments No.

3. S a fety S y stem L o g ic, S etp o in ts and Delay Times (also called "Groundrules disribti onl wifth corraeersponing document") for the last reload fo r:

1. ESFAS See Table 5 See Table 5 See Table 5

2.

RPS See Table 5 See Table 5 See Table 5

3.

SGIS/MSIS See Table 5 See Table 5

See Table 5

4.

PORV See Table 5 See Table 5 See Table 5

5.

SRV.

See Table 5 See Table 5 See Table 5

4. Primary and Secondary-

4. Pressure Drops

1. Primary.side pressure drop distribution with corresponding flow rate, including leakage Later Later Later flows (from design data or, vendor analyses).

2.

Secondary side pressure drop distribution with corresponding flow rate, including leakage Later Later Later flows (from design data or vendor analyses).

5.

Core and Fuel Design

1. Number of assemblies N/A 217

2.

imesios.

/AArray:

16 x 16, The pitch is the sum of

2.

imesios.

/APitch:

8.180 in, 7.972 and 0.208 = 8.180

L-2009-069 Page 9 of 49 Item Parameter -Description Units Value Comments No.

Length: 158.5 in in.

3. Spacer grid locations and K-N/A See Table 4 for Spacer grid K-factors to factors grid locations.

be provided later.

4.

Vessel pressure drops Current values:

a) Inlet nozzle & 90 a) 5.0 degree turn, b) 10.4 b) Downcomer, lower c) 13.4 plenum, support structure, d) 6.7 c) Fuel assembly, d) Fuel assembly outlet to outlet nozzle.

5. Bypass and leakage flows

% of total See item la.5.5 Similar to Item la.5.5 flow above above.

6. Number and location of fuel 236 per assy Some fuel rods contain rods.

N/A 51,212 total.

burnable absorber See Figs. 3 and 4 below for location.

material.

7. Number and location of guide tubes.

5 guide tubes per assy.

See Fig. 3 below for location.

N/A

6.

Equipment Drawings and Design Reports To confirm the calculation of flow path lengths and elevations, flow areas, volumes, metal mass and surface areas (including pipe schedules), and form loss (due to bends, contractions, expansions, orifices, etc.) for the following

L-2009-069 Page 10 of 49 Item Parameter -Description Units Value Comments No.

equipment:

1. Reactor vessel and internals (identification of all core bypass flow paths and flow rates, See Table 3 including upper plenum or head to downcomer, if available).

2.

Primary loop piping (hot leg, See Table 3 cold leg, pump suction)

3. Reactor coolant pumps See Table 3

4.

Steam generators and internals (U-tube lengths, separators, inlet See Table 3 and outlet plenum, etc.), (TH Design Report)

5.

Pressurizer, surge line, spray lines, safety and relief valves See Table 3 and connecting lines, etc.

6. Main steam lines out to the turbine stop valves, including safety and relief valves and connecting lines, main steam isolation valves, flow restrictors, etc.

7.

Main feedwater lines from the isolation valves to the steam See Table 3 generator inlet.

8. Auxiliary feedwater lines and feedwater pump type, See Table 3 configuration and capacity.

9. Safety injection equipment including SITs, high and low See Table 3 pressure injection systems and

L-2009-069 Page 11 of 49 Item Parameter -Description Units Value Comments No.

connecting piping.

10. Charging and letdown system See Table 3 (CVcS).

11. Residual heat removal system.

See Item 6.9 for LPSI See Comments System. LPSI and RHR are the same system.

7.

Reactor Vessel Internals Weight and surface area of reactor vessel internal structures:

8.

Core support barrel Includes upper, center, 136,600 /

and lower portions of the Lbs / sq. ft.

1126 Inside core support barrel; 1110 outside upper and lower flange; inner and outer nozzle areas.

9.

Core shroud 34,000 /

Includes vertical and Lbs / sq. ft.

594 Inside horizontal surfaces of the 867 outside core shroud.

10. Lower core support plate Includes top and bottom Lbs / sq. ft.

8,000 / 260 surfaces; surface areas inside the holes of the plate.

11. Fuel alignment plate (Upper Includes top and bottom Core Plate)

Lbs/sq. ft.

9,900/33 1 surfaces; surface areas inside the holes of the plate.

12. Upper guide structure Includes CEA shrouds with extensions; total UGS plate, flange, beam, Lbs / sq. ft.

120,000 / 7,120

& c ln er ar ea to al

& cylinder areas; total fuel alignment plate area (Neglects guide tubes).

L-2009-069 Page 12 of 49 Item Parameter -Description Units Value Comments No.

13. Core support assembly Includes vertical webs; 0/1193 flanges; cylinder; Lbs sq. ft.

45,500 /11 columns; core support plate; bottom plate.

14. Flow skirt Includes top and bottom Lbs /sq. ft.

3,600 /223 surfaces; surface areas inside the holes of the plate.

15. Control element assembly 48,000/

Does not include (CEA) shrouds Lbs sq. ft.

1826 Inside Doesunottinclude 2100 outside shroud extensions.

16. Shroud extensions 10,400 /

Lbs sq. ft.

866 Inside 1035 outside

17. rid sseblie Lb sq.ft.

18.5 5.0per rid Each assembly has9

17. ridassmblis Ls s. ft 185 /5.0 er rid grids for 217 assemblies.

8.

Steam Generator Internals

1. Weight of steam generator tube sheet and surface area of tube sheet exposed to primary side fluid.

1.1. Weight of Tube Sheet Weight with integral lbm 93,230 forged lower cylindrical ring and cladding 1.2. Surface area of Tube Sheet LaterPRELIMINARY (Primary Side) ft 2

Later72.29 Estimated from tubesheet OD minus 2X tube OD

2.

Weight and surface area of steam generator wrapper.

2.1. Weight of SG wrapper lbm 34,730 Includes wrapper roof

L-2009-069 Page 13 of 49 Item Parameter -Description Units Value Comments No.

2.2. Surface area of SG wrapper ft2

-1360Later LaterWetted surface area on downcomer side Steam Generator Fluid

1. Inlet plenum ft3 338.4 Includes Manway

2.

Outlet plenum ft3 332.0 Includes Manway

3.

Active and 1230.0 inactive (within tube sheet) ft3 41.3 tubes

4. Number of steam generator 8999 tubes

5.

Length of shortest and longest ftin LaterSingle straight leg (not including tubesheet) 262.598 min 273.425 max Later Tube bend radius (to tube centerline) 4.134 min 73.134 max

10.

Steam Generator Parameters

1. Inventory and recirculation ratio Power Secondary versus load (essential at rated Mass Inventory at EPU power conditions)

Ibm 0

215680 conditions. Recirculation 25 184560 ratios provided in Item 50 164650 lb. 1.5 75 150600

L-2009-069 Page 14 of 49 Item Parameter -Description Units Value Comments No.

100 139430

2.

SG flow areas, K-factors and flows Later Later Later

11.

MS Line Flow Restrictor f2 3.791 to 3.803 per OultNzeAra

1. Restrictor flow area t

SG, FuloVenturizl Area, 2.27 per SG

1. Steam Generator and Reactor

12.

Vessel Heights

1. Volume versus height relationship for the steam generators with downcomer and See Table 6 See Table 6 boiler regions provided separately

2.

Volume versus height for the reactor vessel with internals See Table 6 See Table 6 installed Reactor Coolant Pump Rated Conditions

1. Head The value is the average ft 296.75 of the four pump-specific values (303, 296, 293 &

295 fi)

L-2009-069 Page 15 of 49 Item Parameter -Description Units Value Comments No.

2.

Flow The value is the average of the four pump-specific gpm 87,750 values (85,000 - 87,500 -

91,000 & 87,500 gpm)

3.

Torque The value is the average lbf-ft 33,950 of the four pump-specific values (33,860 - 34,000

- 34,720 & 33,230 ft-lbf)

4. Speed rpm 900 Synchronous speed

5.

Density The value is the average ibm! ft3 4of the four pump-specific values (47.3, 47.4, 46.9 and 48.4 Ibm/

)

6.

Homologous pump curves (four N/A See Table 7 quadrant)

7.

Pump inertia and friction Uncertainty value of+

(coefficients of polynomial in 1% may be applied to pump speed) lbm-ft2 102,000 pump inertia in the analysis to gain ft-lbf 2735 operating margin.

- Constant for friction and windage torque.

8.

Coolant primary system fluid ft3 112 volume within pump

9.

RCP metal mass, excluding lbs 75,000 Dry weight.

motor

10. Reverse rotation device RCP design torque for operational for RCPs N/A Yes anti-reverse rotation device equal to 62,000 ft-lbf.

11. Pump power to primary fluid MWt 14.2 (nominal),

L-2009-069 Page 16 of 49 Item Parameter -Description Units Value Comments No.

20 (max)

12. Coastdown characteristics N/A Figure 2

13. Pump trip setpoints N/A Overcurrent Overload Trip

14. Pump time delays and logic N/A N/A No safety related RCP trips.

14.

Core Cooling System

1. HPSI and LPSI delivery curves See Tables 8, 9, 10, gpm 11

2.

SIT total volume 3

1855 Four tanks, each with this capacity.

3. SIT initial pressure and liquid psia (500 to 650 + 15)

TS ranges for SIT volume W

f 3

(1420 to 1556 +

pressure and liquid

32) volume.

4.

CST minimum capacity gal 276,200

5.

Charging pump flow versus Reciprocal pump. Flow pressure 40 (nominal) to 49 is per charging pump.

gpm (maximum)

Nominal value does not 35 minimum, after include 4 gpm for RCP uncertainties bleed-off.

15.a Control Sysem Rated power operation of the primary and secondary control systems for:

1. SG water level instrumentation Later Later Later and control (three-element)

2.

SG pressure (including bypass Later Later Later and ADV)

3. Pressurizer heaters and sprays Later Later Later

4. Pressurizer level Later Later Later

L-2009-069 Page 17 of 49 Item Parameter -Description Units Value Comments No.

5. Auxiliary feedwater Later Later Later

6. CVCS (charging and letdown)

Later Later Later 15.b Control Systems EPUrconditione oeration of the L

Later piayand seonarVcnto systems for:

7.

SG water level instrumentation LtrLtr ae and control (three-element)

8. SG pressure (including bypass Later Later Later and ADV)

9. Pressurizer heaters and sprays Later Later Later

10. Pressurizer level Later Later Later

11. Auxiliary feedwater Later Later Later

12. CVCS (charging and letdown)

Later Later Later

16.

Reactor Vessel Upper Head

1. Upper head fluid temperature at normal operating conditions.

17.

Essential Valve Characteristics Number of valves, full open flow area, forward/ reverse flow coefficients (CV's), open/close rate, minimum flow at rated conditions, logic for opening and OF Assume to be the same as the core outlet Later temperature since the Rx vessel does not have

L-2009-069 Page 18 of 49 Item Parameter -Description Units Value Comments No.

closing the valves for:

1. Pressurizer PORVs See Table 12

2. Pressurizer safety valves See Table 12

3. Main steam safety valves See Table 12

4. Atmospheric dump valves See Table 12

5. TCVs (turbine control valves)

See Table 12

6. Turbine bypass valves See Table 12

7. TSVs, (turbine stop valves)

See Table 12

8. MFIVs See Table 12

9. MSIVs See Table 12 18.

to Reactor Core Parameters 20.

1. Control rod insertion versus time atrsrmLater Later Later after scram

2. CEA worth versus insertion (with and without highest worth Later Later Later rod stuck out of core)

3. Reactivity versus fuel temperature and reactivity Later Later Later versus moderator density

4.

Moderator temperature Later Later Later coefficient

5. Typical top peaked axial power Later Later Later profile

6. Minimum and maximum average fuel clad gap Later Later Later conductivity at rated power conditions

L-2009-069 Page 19 of 49 Item Parameter -Description Units Value Comments No.

7.

Minimum local gap conductance Later Later Later as a function of LHGR

8.

Gap conductance Later Later Later

9.

Linear heat rate Later Later Later

10. Fuel average and centerline temperature as a function of Later burnup for the hot rod in the hot bundle.

Operator Actions During

1. Reactor coolant pump trips Accident analysis (conditions to trip pumps -

assumes LOOP automatic or manual)

Pumps concurrent with LOCA, None automatically trip and pumps are not Nuomcl t

loaded into EDGs or manually operated. Same assumption for EPU analysis.

2.

HPSI throttling criteria If HPSI pumps are operating, and ALL of the following conditions are satisfied:

None See Comments n

RCS subcooling is Section.

greater than or equal to minimum subcooling

Pressurizer level is at least 30%

and NOT lowering,

L-2009-069 Page 20 of 49 item Parameter -Description Units Value Comments No.

- At least ONE S/G is available for RCS heat removal with level being restored to or maintained between 60 and 70% NR,

- Rx Vessel level indicates sensors 4 through 8 are covered, or NO abnormal differences (greater than 20'F) between THOT and Rep CET temperature, Then, THROTTLE SI flow. Same assumption for EPU analysis.

3.

MS line break auxiliary Due to the design of the feedwater control AFW system that automatically isolates the AFW from the broken N/A See comment loop, no auxiliary feedwater was assumed to be delivered during the post-trip MSLB event. No flow delivered for pre-trip MSLB either.

Most recent COLR provided to NRC via See FPL letter L-2007-183,

22.

Core Operating Limits Report Comment See Comment dated 11-19-2007. EPU COLR to be provided later after it is issued.

L-2009-069 Page 21 of 49 Item Parameter -Description Units Value Comments No.

23.

RCS Material Property Data For the various materials in the

[=

reactor coolant system (stainless s*

=,-

steel, inconel, etc.):

+ ;s......*,,*

'*=I

'¢i

=

1. Density lb/ft3 See Table 15

2. Specific heat BTU/lIbm-°F See Table 15

3.

Thermal conductivity BTU/hr-ft-OF See Table 15 4.2. Emissivity versus temperature See Table 15

L-2009-069 Page 22 of 49 Figure 1 ST. LUCIE UNIT 2 PRESSURIZER LEVEL PROGRAM Note: The Values Refer to the Actual Plant Settings PRESSURIZER LEVEL PROGRAM 65 (571.2, 63.0) 60 t 55 t C.

CL a.

I-

-J w

w

,-J w

N CL u..

50 t 45 f 40 +

35 t (538.2, 33.1) 30 -

25 I

I I

520.0 530.0 540.0 550.0 560.0 570.0 580.0 TAVE (F) 590.0 Pressurizer Volume at 63.0% Span is 914 Cu. Ft.

Pressurizer Volume at 33.1% Span is 463 Cu. Ft.

L-2009-069 Page 23 of 49 Figure 2 - RCP Coastdown 800 700

-CI)

600 0

(05 400 NJ0 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 2 FIGURE 15.3.2-1 Complete Loss of Flow -

Four Pumps Coasting Down Total Core Inlet Flow versus Time 15.3-10 Amendment No. 17 (12/06)

Note: Curve represents current analyses.

L-2009-069 Page 24 of 49 Figure 3 CORE SUPP(

BARREL

L-2009-069 Page 25 of 49 Figure 4 W

V T

S RPNM LK J HG I I IllI 1F-13 7T-17EIiS-131 U325 T85 1"40 XSI j 02 1(54 E-15 L-15 V-6 FEED FEED FEED T1 I37 X56 X66 UX11U661U20 XBS X62 G-16 E-8 FEED FEED 0-17

-2 VU17I FEED FEED T38 IT28.

T-6 G-6 T21I MIXII X1108 IU431 X314 U221 I36 1U37 I03 IX16I X46 T27 F-15 FEED FEED N-2 V-9 FEED L-13 FEED D-9 J-2 FEED FEED F-7 1327 1-6 T57 T-5 U335 U23 T42 X18 U48 TO X127 7 T1 U54 T155 X28 T06 147 X-10 T35 U31 R-6 F-5 FEED D4 X-17 FEED R-9 R-3 R-13 FEED B-17 V-4 FEED S-5 G-5 T58 X63 1U0 07 T

,37 MSE U56 T01 U65 T16 X42 T19 1305 X,50 T63 T1-FEED E-13 T-20 FEED H-1 6-19 L-17 F-19 P-i FEED E-20 X13 FEED G-11

,41 X69 U40 131 Tll U53 X12 147 X22 U60 TOE X23 U38 X70 T29 F-1 PEED J-18 FEED A-8 G-3 FEED G-7 FEED W-7 Y-8 FEED N-18 FEED S-18 X64 U34 X43T9 U5 0 X19 1T52 X04 T45 X20 U68 T72

)(33 1,12 X52 FEED T-FEED N-7 W-16 FEED W-11 FEED L-19 FEED C-16 N-I5 FEED E4 FEED E

US T02 T51 T(06 Sp XO7 T50 T03 U52 U09 U62 )001 FEED &11 N-il C-7 1T-11 -15 FEED E-13 FEED R-7 E-11 W-15 J.11 X-11 FEED 21

-20

-17

-15 U3a -- 13

~-13 162 E-5 1313 -L J-16

-~7 6

270, X5E IllI(X44 1T61 U57 I X15 I T49 IX08 FEEDI T-18 IFEEDI J-7 IW-6 FEED L-3 FEED T48 X17 U49 T56 X-351 U18 1X60 C-11 FEED C-6 J-15 FEED E-18 FEED F-

-l T34 IX7 I U39 )1 T13 IU61I X26 I T46 I X14 I U58 T12 I 3X13 U44 X65 I T31

-4IFEED J-4 FEED A-14 C-15 FEED R-15 FEED R-19 Y-14 FEED N-4 FEED S-4 I T14 X40 T20 1U13 T04 U67 T18 X41 T17 U07 1581T68 R-Il FEED U-9 T-2 FEED H-21 S-3 L-5 F-3 P-21 FEED E-2 IX-9 FEED L-4 U29IT35I(301U46 T15 X29 T70 IU64 T60 IX25 TI0 1U45 1)(321 T33 I U30 R-17 F-l7 FEED D-18 X-5 FEED G-9 G-19 G-13 FEED B-5 V-16 FEED S-17 G-17 T26 I X47 I(24I U02 I U41I X38 IU316I X39 I1U42 I U04 I X21 IX48 I T25 S-15 FEED FEED N-20 V-13 FEED L-9 FEED 0-13 J-20 FEED FEED S-7

-65

-4 T24 I43I X53I X72I U14I U51I U26 IX67 1(551T30 T 22 R-16 E-16 FEED FEED D-5 L-20 V-6 FEEDFEED 1-t6 RI-6 U32 T67 T32 IX49 IX03 X61 IT44 I64 T

I13 E-7 V-11 V-16 FEED FEED FEED D-16 L-7 T-7 3

2 Frm Cycle 15 "From Cycde 14

.Assembly Identifier Previous Cycle Location 180*

1.115 1T54 IS551 1328 __________________

F-S 1.5 eS S-S 18ET FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 2 CYCLE 17 REFERENCE CORE LOADING PATTERN FIGURE 4.3-65 Amendment No. 18 (01/08)

L-2009-069 Page 26 of 49 Table 1 (Later)

L-2009-069 Page 27 of 49 Table 2 (Later)

L-2009-069 Page 28 of 49 Table 3 Unit 2 Piping Isometric Drawings by P&ID Flow Diagram Component/Isometric Drawing Reactor Vessel 2998-G-078, Sheet 110, Rev. 08 2998-769, Rev: 2 Primary Loop Piping (RCS) 2998-G-078, Sheet 110, Rev. 08 2998-2662, Rev. 4 2998-2132, Rev. 6 2998-3793, Rev. I 2998-1887, Rev. 3 2998-1886, Rev. 6 Reactor Coolant Pumps 2998-G-078, Sheet 1I1A, Rev. 11 2998-455, Rev. 6 2998-G-078, Sheet 111 B, Rev. 10 2998-457, Rev. 8 2998-G-078, Sheet I111IC, Rev. 13 2998-G-078, Sheet 11 ID, Rev. 10 Steam Generators 2998-G-078, Sheet 110, Rev. 8 f 2998-21342 Rev 0 (Later) 2998-G-079, Sheet 1, Rev. 41 2998-G-080, Sheet 2A, Rev. 43 Pressurizer/Surge Line/Spray Lines/Relief Lines 2998-G-078, Sheet 109, Rev. 18 2998-506, Rev 4 2998-G-078, Sheet 108, Rev. 5 2998-G-125, Sheet RC-AB-1, Rev 13 2998-G-125, Sheet RC-AB-2, Rev 11 2998-2048, Rev 5 Main Steam Lines Out to the Turbine Stop Valves 2998-G-079, Sheet 1, Rev. 41 2998-G-125, Sheet MS-L-1, Rev. 22 2998-G-079, Sheet 2, Rev. 35 2998-G-125, Sheet MS-L-2, Rev. 22 2998-G-125, Sheet MS-L-3, Rev. 10 2998-G-125, Sheet MS-L-4, Rev. 16 2998-G-125, Sheet MS-L-13, Rev. 11 2998-G-125, Sheet MS-L-14, Rev. 16 Main Feedwater Lines from the Isolation Valves to the Steam Generator Inlet 2998-G-080, Sheet 2A, Rev. 43 J 2998-G-125, Sheet BF-M-6, Rev. 17 Auxiliary Feedwater Lines 2998-G-080, Sheet 2B, Rev. 36 2998-G-125, Sheet BF-M-7, Rev. 18 2998-G-125, Sheet BF-M-8, Rev. 20 2998-G-125, Sheet BF-M-9, Rev. 16 Safety Injection 2998-G-078, Sheet 130A, Rev. 19 2998-G-078, Sheet 130B, Rev. 28 2998-G-078, Sheet 131, Rev. 20 2998-G-078, Sheet 132, Rev. 09 2998-G-1.25, Sheet SI-N-4, Rev. 20 2998-G-125, Sheet SI-N-5, Rev. 19 2998-G-125, Sheet SI-N-6, Rev. 18 2998-G-125, Sheet SI-N-7, Rev. 15

L-2009-069 Page 29 of 49 2998-G-078, Sheet 110, Rev. 08 2998-G-125, Sheet SI-N-8, Rev. 18 2998-G-125, Sheet SI-N-9, Rev. 20 2998-G-125, Sheet SI-N-14, Rev. 25 2998-G-125, Sheet SI-N-16, Rev. 17 2998-G-125, Sheet SI-N-17, Rev. 14 2998-G-125, Sheet SI-N-18, Rev. 12 2998-G-125, Sheet SI-N-19, Rev. 15 2998-G-125, Sheet SI-N-20, Rev. 14 2998-G-125, Sheet SI-N-21, Rev. 13 2998-G-125, Sheet CS-K-i, Rev. 19 2998-G-125, Sheet CS-K-2, Rev. 20 2998-C-124, Sheet SI-1, Rev. 12 2998-C-124, Sheet SI-2, Rev. 10 2998-C-124, Sheet SI-3, Rev. 12 2998-C-124, Sheet SI-4, Rev. 13 2998-C-124, Sheet RC-1, Rev. 9 2998-C-124, Sheet RC-2, Rev. 13 Charging and Letdown System (CVCS) 2998-G-078, Sheet 110, Rev. 08 2998-G-078, Sheet 120, Rev. 17 2998-G-078, Sheet 121A, Rev. 31 2998-G-078, Sheet 122, Rev. 25 2998-G-125, Sheet CH-G-1, Rev. 21 2998-G-125, Sheet CH-G-2, Rev. 19 2998-G-125, Sheet CH-G-3, Rev. 16 2998-G-125, Sheet CH-G-4, Rev. 21 2998-G-125, Sheet CH-G-10, Rev. 12 2998-G-125, Sheet CHG--14, Rev. 11 2998-G-125, Sheet CH-G-15, Rev. 15 2998-G-125, Sheet CH-G-16, Rev. 06 2998-G-125, Sheet CH-G-17, Rev. 13 2998-C-124, Sheet CH-1, Rev. 11 2998-C-124, Sheet CH-3, Rev. 12 2998-C-124, Sheet CH-4, Rev. 09 2998-C-124, Sheet CH-6, Rev. 8 2998-C-124, Sheet CH-33, Rev. 7 2998-C-124, Sheet CH-72, Rev. 15 2998-C-124, Sheet CH-75, Rev. 14 2998-C-124, Sheet CH-78, Rev. 12 2998-C-124, Sheet CH-103, Rev. 9 2998-C-124, Sheet CH-104, Rev. 8 2998-C-124, Sheet CH-105, Rev. 6 2998-C-124, Sheet CH-106, Rev.. 13 2998-C-124, Sheet CH-108, Rev. 7 2998-C-124, Sheet CH-109, Rev. 17 2998-C-124, Sheet CH-1 10, Rev. 14 2998-C-124, Sheet CH-11, Rev. 11 2998-C-124, Sheet CH-112, Rev. 13 2998-C-124, Sheet CH-129, Rev.,O 2998-C-124, Sheet RC-2, Rev. 13

L-2009-069 Page 30 of 49 Table 4 Spacer Grid Locations Grid #

Distance (in) 1 5.175 2

22.375 3

38.188 4

54.000 5

69.812 6

85.625 7

101.438 8

117.250 9

133.062 10 148.875 Notes: Measured from bottom of fuel assembly to top of grid.

L-2009-069 Page 31 of 49 Table 5 RPS, ESFAS and AFAS Setpoints and Safety Analysis Limits Functional Description Monthly Tech Spec Setpoint Current Setpoint or EPU Setpoint or Comments Surveillance Uncertainty Requirement Uncertainty Setpoint (current cycle)

Requirement RPS PZR Press Hi 2360 psia

< 2370 psia

+ 45 psi (Normal)

+/- 45 psi (Normal)

+ 90 psi (Accident)

RPS Cont. Press Hi 2.5 psig

< 3.0 psig

+ 1.65 psi

+ 1.65 psi RPS S/G Press Lo 626 psia

> 626 psia

+/- 40 psi (Normal)

+ 80 psi (Accident)

+/- 80 psi (Accident)

RPS S/G Level Lo 20.5%

> 20.5%

+ 5% (Normal)

+/- 5% (Normal)

+/- 14% (Accident)

RPS RCS Low Flow

> 95.4% Design 3.5%

3.5% (Normal)

Flow 7.5% (Accident)

SIAS/CIS Cont. Press Hi 3.41 psig

< 3.5 psig

+/- 1.65 psi

+/- 1.65 psi CSAS Cont. Press Hi-Hi 5.31 psig

< 5.4 psig

+/- 1.65 psi

+/- 1.65 psi SIAS PZR Press Lo 1740 psia

> 1736 psia

+ 45 psi (Normal)

+/- 45 psi (Normal)

+ 90 psi (Accident)

MSIS S/G Press Lo 600 psia

> 600 psia

+/- 40 psi (Normal)

+ 40 psi (Normal)

+/- 80 psi (Accident)

RAS RWT Level Lo 5.67 feet 5.67 feet

+/- 6 inches

+ 6 inches AFAS S/G Level Lo 19.5%

> 19.0%

+/- 5% (Normal)

+/- 14% (Accident)

AFAS S/G Press DP Hi 270 psid

< 275 psid Not specified

+/- 60 psi (Normal)

+/- 115 psi (Accident)

AFAS FW Press DP Hi 142.5 psid

< 150.0 psid Not specified

< 245 psid (setpoint)

EPU setpoint requirement based on

+/- 85 psi (Normal) uncertainty AFAS logic time delay 210 sec 120 sec 120 sec (minimum actuation time)

PORV Open Pressure N/A 2370 psia (nominal) 2370 psia (nominal)

For non-LTOP conditions, PORVs (setpoint) operate on RPS PZR Press Hi Main Steam Safety RV N/A 1000 psia (nominal)

+/- 3% (Bank 1 tolerance)

+/- 3% (Bank I tolerance) 1040 psia (nominal)

+2%, -3% (Bank 2 tol.)

1 3% (accumulation) 3% (accumulation)

PZR Safety RV N/A 2500 psia (nominal)

+/- 3% (tolerance)

+/- 3% (tolerance) 1 3% (accumulation) 3% (accumulation)

Note: When revised, Safety Analysis limits are set equal to the Tech Spec setpoint plus or minus the defined uncertainty.

L-2009-069 Page 32 of 49 Table 6 REACTOR COOLANT SYSTEM GEOMETRY Component Hot Leg Suction Leg Discharge Leg Parallel Non-parallel Reactor Coolant Pump Pressurizer Liquid level Surge Line Steam Generator Inlet nozzle (ea)

Inlet plenum Tubes (active and passive)

Outlet plenum Outlet nozzle (ea)

Reactor Vessel Inlet nozzles Downcomer Lower plenum Lower support structure and inactive core Active core Upper inactive core Outlet plenum CEA shroud UGS annulus, outside CEA shroud Top Head Outlet nozzles Top Flow Path Elevation Length (ft)

(ft's (d) 14.53 2.38 22.83 1.04 16.39 16.42 22.81 54.51 2.23 4.64 56.81 5.50 1.72 3.6 20.9 6.4"')

3.5 11.4 1.5 11,00()

12.2(g) 4.5 4.1 1.25 1.25 1.25 47.20 30.66 10.83 2.24 6.91 37.65 6.91 1.39 1.5 1.5

-20.9

-17.4

-6.0

-4.5 2.0 9.8 6.5 13.0 2.0 Bottom Elevation (ft) W

-1.75

-7.25

-1.25

-1.79 10.83 10.83 1.75 0.95('e 0.36 6.91 0.36 0.16(e)

-1.5

-20.9

-27.0

-20.9

-17.4

-6.0

.-4.5 2.0 2.0 6.5

-2.0 Minimum Flow Volume Area Wft

2)

Wft3) 9.62 139.81 4.91 112.07 4.91 80.46 4.91 80.52 4.91(0 112 1500 50.07(')

800 0.56 29.30 9.62 21.77 61.04 342.94 0.00241c) 1247.71 61.04 337.95 4.91 8.58 4.9 78 30.3 674 43.7 702 28.0 473 54.8 669 47.1 85 23.45 524 430 122 753 9.62 105 Amendment No. 18 (01/08) 4.4-47

L-2009-069 Page 33 of 49 Table 6 - Continuation TABLE 4.4-8 (Cont'd)

Notes:

(a)

For the cylinder (b)

Represents a geometrical rather than an actual flow path length (c)

Flow path area per tube (d)

Reactor vessel nozzle centerline is the reference elevation; it has an elevation of 0.0 ft.

(e)

Nozzle centerline (M

RCP outlet (g)

Approximate flow path length 4.4-48

L-2009-069 Page 34 of 49 Table 7 Reactor Coolant Pump Homologous Curves VALPHA HAN HVN BAN BVN VALPHA HAD HVD BAD BVD 0.0 1.5800

-1.4200 0.7700

-1.4500 0.0 1.5800 1.2200 0.7700 1.3150 0.1 1.5000

-1.2150 0.8020

-1.1120

-0.1 1.6600 1.2850 0.8100 1.3800 0.2 1.4200

-1.0820 0.8450

-0.8720

-0.2 1.7600 1.3450 0.8800 1.4500 0.3 1.3700

-0.9120 0.8660

-0.6480

-0.3 1.8700 1.4400 0.9800 1.5100 0.4 1.3300

-0.7280 0.8850

-0.4420

-0.4 2.0000 1.5500 1.0900 1.5800 0.5 1.2950

-0.4940 0.9100

-0.2700

-0.5 2.1300 1.7200 1.2350 1.6400 0.6 1.2700 0.0000 0.9300 0.2600

-0.6 2.3000 1.9300 1.3900 1.7200 0.7 1.2400 0.2080 0.9530 0.4300

-0.7 2.4700 2.1800 1.5800 1.8300 0.8 1.1820 0.4350 0.9730 0.6130

-0.8 2.7000 2.4900 1.7850 1.9600 0.9 1.1050 0.7080 0.9890 0.8000

-0.9 2.9300 2.8100 2.0400 2.1200 1.0 1.0000 1.0000 1.0000 1.0000

-1.00 3.1500 3.1500 2.2900 2.2900 VALPHA HAT HVT BAT BVT VALPHA HAR HVR BAR BVR 0.0 0.4330 1.2200

-1.4400 1.3150 0.0 0.4330

-1.4200

-1.4400

-1.4500 0.1 0.4740 1.1820

-0.9200 1.2450

-0.1 0.3430

-1.7150

-1.6600

-1.8500 0.2 0.5020 1.1400

-0.6300 1.1800

-0.2 0.0112

-1.9600

-1.9100

-2.2000 0.3 0,5120 1.0850

-0.4200 1.1100

-0.3

-0.2460

-2.1500

-2.1900

-2.5200 0.4 0.5240 1.0450

-0.2500 1.0420

-0.4

-0.5130

-2.3400

-2.4900

-2.8500 0.5 0.5460 1.0000

-0.1000 0.9750

-0.5

-0.8300

-2.5200

-2.8300

-3.1500 0.6 0.5830 0.9500 0.0200 0.9050

-0.6

-1.0350

-2.6900

-3.2400

-3.4900 0.7 0.6410

- 0.9000 0.1300 0.8170

-0.7

-1.6000

-2.8100

-3.6000

-3.8400 0.8 0.7120 0.8700 0.2510 0.7280

-0.8

-2.0500

-2.9300

-4.0500

-4.2300 0.9 0.8000 0.8650 0.3900 0.6280

-0.9

-2.5500

-3.0100

-4.5400

-4.6100 1.0 0.9080 0.9080 0.5620 0.5620

-1.0

-3.1000

-5.0300

-5.0300 Note: According to WEC, the definition of the column headings can be found in the reactor coolant pump model input description in the CEFLASH-4A topical report.

L-2009-069 Page 35 of 49 Table 8 (Sheet 1 of 2)

SL-2 UFSAR ECCS PERFORMANCE DATA ONE LPSI PUMP FAILED TO START EFFECTIVE FOR LARGE BREAK ANALYSIS (LPSIP B Off, Other Pumps On)

RCS Flow to RCS Flow to Pressure Loop Al or Pressure Loop Al or (psia)

A2 (gpm)

(psia)

A2 (gpm) 1408 0

1165 0

1399 28 1158 23 1382 55 1142 45 1337 83 1105 68 1230 110 1068 90 1160 138 1008 113 1070 165 929 135 948 193 824 158 819 220 711 180 680 248 591 203 511 275 445 225 334 303 290 248 184 700 166 261 178 800 162 262 173 850 157 262 166 950 150 263 158 1050 143 264 149 1150 135 370 139 1250 125 660 128 1350 116 825 116 1450 105 990 103 1550 93 1080 89 1650 81 1170 74 1750 67 1260 58 1850 52 1350 39 1900 35 1440 20 2000 18 1530 0

2050 0

1620

L-2009-069 Page 36 of 49 Table 8 (Sheet 2 of 2)

SL-2 UFSAR ECCS PERFORMANCE DATA ONE LPSI PUMP FAILED TO START EFFECTIVE FOR LARGE BREAK ANALYSIS (LPSIP B Off, Other Pumps On)

MAXIMUM MINIMUM RCS Flow to RCS Flow to Pressure Loop B1 or Pressure Loop B1 or (psia)

B2 (gpm)

(psia)

B2 (gpm) 1408 0

1165 0

1399 28 1158 23 1382 55 1142 45 1337 83 1105 68 1230 110 1068 90 1160 138 1008 113 1070 165 929 135 948 193 824 158 819 220 711 180 680 248 591 203 511 275 445 225 334 303 290 248 121 330 105 270 0

341 0

279

L-2009-069 Page 37 of 49 Table 9 (Sheet 1 of 2)

SL-2 SAFETY INJECTION DATA ONE EMERGENCY GENERATOR FAILED TO START EFFECTIVE FOR NON-LOCA ANALYSES (HPSIP B & LPSIP B Off, Other Pumps On)

MAXIMUM MINIMUM RCS Flow to RCS Flow to Pressure Loop Al or Pressure Loop Al or (psia)

A2 (gpm)

(psia)

A2 (gpm) 1408 0

1165 0

1399 14 1158 12 1382 28 1142 23 1337 42 1105 34 1230 55 1068 45 1160 69 1008 57 1070 83 929 68 948 97 824 79 819 110 711 90 680 124 591 102 511 138 445 113 334 152 290 124 184 650 167 130 183 700 165 130 177 750 161 130 170 850 154 131 162 950 146 131 151 1100 137 280 141 1250 127 570 128 1400 116 760 116 1500 105 900 101 1600 91 990 85 1700 77 1080 68 1750 62 1170 49 1850 45 1260 30 1950 28 1350 8

2000 7

1440 0

2050 1

0 1535

L-2009-069 Page 38 of 49 Table 9 (Sheet 2 of 2)

SL-2 SAFETY INJECTION DATA ONE EMERGENCY GENERATOR FAILED TO START EFFECTIVE FOR NON-LOCA ANALYSES (HPSIP B & LPSIP B Off, Other Pumps On)

MAXIMUM MINIMUM RCS Flow to RCS Flow to Pressure Loop B1 or Pressure Loop B1 or (psia)

B2 (gpm)

(psia)

B2 (gpm) 1408 0

1165 0

1399 14 1158 12 1382 28 1142 23 1337 42 1

1105 34 1230 55 1068 45 1160 69 1008 57 1070 83 929 68 948 97 824 79 819 110 711 90 680 124 591 102 511 138 445 113 334 152 290 124 122 165 105 135 0

168 0

138

L-2009-069 Page 39 of 49 Table 10 SL-2 SAFETY INJECTION DATA NO FAILURE IN ECCS EFFECTIVE FOR NON-LOCA ANALYSIS (All Pumps On)

MAXIMUM MINIMUM RCS Flow to RCS Flow to Pressure Loop Al, A2 Pressure Loop A1, A2 (psia)

B1 or B2 (psia)

B1 or B2 1408 0

1165 0

1399 28 1158 23 1382 55 1142 45 1337 83 1105 68 1230 110 1068 90 1160 138 1008 113 1070 165 929 135 948 193 824 158 819 220 711 180 680 248 591 203 511 275 445 225 334 303 290 248 184 700 166 261 178 800 162 262 173 850 157 262 166 950 150 263 158 1050 143 264 149 1150 135 370 139 1250 125 660 128 1350 116 825 116 1450 105 990 103 1550 93 1080 89 1650 81 1170 74 1750 67 1260 58 1850 52 1350 39 1900 35 1440 20 2000 18 1530 0

2050 0

1620

L-2009-069 Page 40 of 49 Table 11 (Sheet 1 of 2)

SL-2 UFSAR ECCS PERFORMANCE DATA ONE EMERGENCY GENERATOR FAILED TO START EFFECTIVE FOR SMALL BREAK ANALYSIS (HPSIP B & LPSIP B Off, Other Pumps On)

MAXIMUM MINIMUM RCS Flow to RCS Flow to Pressure Loop Al or Pressure Loop Al or (psia)

A2 (gpm)

(psia)

A2 (gpm) 1408 0

1198 0

1399 14 1382 28 1337 42 1230 55 1160 69 1070 83 948 97 819 110 680 124 511 138 334 152 184 650 183 700 177 750 170 850 162 950 151 1100 141 1250 128 1400 116 1500 101 1600 85 1700 68 1750 49 1850 30 1950 8

2000 0

2050 1177 25 1104 50 1035 62.5 943 75 829 87.5 699 100 551 112.5 393 125 217 137.5 167 140.6 165 140.7 161 141.0 154 141.4 146 141.9 137 291 127 580 116 770 105 910 91 1000 77 1090 62 1181 45 1271 28 1362 7

1453 0

1548

L-2009-069 Page 41 of 49 Table 11 (Sheet 2 of 2)

SL-2 UFSAR ECCS PERFORMANCE DATA ONE EMERGENCY GENERATOR FAILED TO START EFFECTIVE FOR SMALL BREAK ANALYSIS (HPSIP B & LPSIP B Off, Other Pumps On)

MAXIMUM MINIMUM RCS Flow to RCS Flow to Pressure Loop B1 or Pressure Loop B1 or (psia)

B2 (gpm)

(psia)

B2 (gpm) 1408 0

1198 0

1399 14 1382 28 1337 42 1230 55 1160 69 1070 83 948 97 819 110 680 124 511 138 334 152 122 165 0

168 1177 25 1104 50 1035 62.5 943 75 829 87.5 699 100 551 112.5 393 125 217 137.5 0

151

L-2009-069 Page 42 of 49 Table 12 Component Data Required Component Flow Diagram Component Information Pressurizer PORVs V1475V1474 I 2998-G-078 Sheet 108 Rev. 5 2998-18810 Rev. 3 V 1475 I

Pressurizer Safety Valves V1200 2998-G-078 Sheet 109 R18

/ 2998-19690 Rev. 1 V1201 2998-19691 Rev. I VI1202 Main Steam Safety Valves V8201 2998-G-079, Sheet 1, Rev. 41 2998-2381, Rev 11 V8202 V8203 V8204 V8205 V8206 V8207 V8208 V8209 V8210 V821 I V8212 V8213 V8214 V8215 V8216 Atmospheric Dump Valves MV-08-18A 2998-G-079, Sheet 1, Rev. 41 2998-11458 Rev. 10 MV-08-19A MV-08-18B MV-08-19B Turbine Control Valves (Governor)

FCV-08-644 2998-G-079 Sheet 2, Rev.35 2998-2184 Rev. 10 FCV-08-645 2998-31,Rev 17 FCV-08-646 FCV-08-647 Turbine By-Pass Valves PCV-8801 2998-G-079 Sheet 2 Rev. 35 2998-625 Rev. 11 2998-4091 Rev. 2 2998-4092 Rev. I Turbine Stop Valves (Throttle)

FCV-08-640 FCV-08-641 2998-G-079 Sheet 2, Rev.35 2998-2184 Rev. 10 2998-31, Rev 17

L-2009-069 Page 43 of 49 FCV-08-642 FCV-08-643 Main Feed Isolation Valves HCV-09-IA 2998-G-080 Sheet 2A Rev. 43 2998-9486 Rev. 4 HCV-09-IB 2998-9487 Rev. 4 HCV-09-2A HCV-09-2B Main Steam Isolation Valves HCV-08-IA 2998-G-079 Sheet 1, Rev. 41 l 2998-1011 Rev. 3 Sheet 1/9 HCV-08-IB 2998-1012 Rev. 0 Sheet 2/9 Miscellaneous Components V09107 2998-G-080 Sheet 2B Rev.36 2998-20110 Rev. 1 V09108 2998-741 Rev. 3 SE-09-2 2998-13008 Rev. 3 2998-13006 Rev. 1 2998-13009 Rev. 2 MV-09-9 2998-19745 Rev. 2 2998-1872 Rev. 6 2998-5616 Rev. 0 V09119 2998-3033 Rev. 4 V09120 2998-742 Rev. 2 V09123 2998-20110 Rev. 1 V09124 2998-741 Rev. 3 SE-09-3 2998-13008 Rev. 3 2998-13006 Rev. 1 2998-13009 Rev. 2 MV-09-10 2998-19745 Rev.2 2998-1872 Rev. 6 2998-5617 Rev. 0 V09135 2998-3033 Rev. 4 V09136 2998-742 Rev. 2 V09139 2998-752 Rev. 5 V09140 2998-751 Rev. 2 SE-09-4 2998-13007 Rev. 1 2998-13008 Rev.3 2998-13009 Rev. 2 MV-09-11 2998-19745 Rev. 2 2998-1871 Rev. 7 2998-5617 Rev. 0 V09151 2998-3033 Rev. 4 V09152 2998-742 Rev. 2 SE-09-5 2998-13007 Rev. I 2998-13008 Rev.3 2998-13009 Rev. 2 MV-09-12 2998-19745 Rev. 2 2998-1871 Rev. 7 2998-5616 Rev. 0 V09157 2998-3033 Rev. 4

L-2009-069 Page 44 of 49 V09158 V3225 V3624 V3258 V3227 V3215 V3614 V3259 V3217 V3245 V3644 V3261 V3247 V3235 V3634 V3260 V3237 FE-3312 HCV-3615 V3114 V3805 FE-3311 V3113 HCV-3616 HCV-3617 FE-3322 HCV-3625 V3124 HCV-3626 FE-3321 V3766 HCV-3627 FE-3332 HCV-3635 V3134 FE-3331 V3133 HCV-3636 HCV-3637 FE-3342 2998-G-078 Sheet 132 Rev. 9 2998-G-078 Sheet 131 Rev. 20 2998-742 Rev. 2 2998-19174 Rev. 2 2998-4353 Rev. 5 2998-784 Rev. 6 2998-655 Rev. 1 2998-658 Rev. 1 2998-19174 Rev. 2 2998-4353 Rev. 5 2998-784 Rev. 6 2998-655 Rev. 6 2998-658 Rev. 1 2998-4353 Rev. 5 2998-19174 Rev. 2 2998-784 Rev. 6 2998-655 Rev. 1 2998-658 Rev. 1 2998-19174 Rev. 2 2998-4353 Rev 5 2998-784 Rev. 6 2998-655 Rev. 1 2998-658 Rev. 1 2998-1219 Rev. 9 2998-655 Rev. 1 2998-2076 Rev. 19 2998-19800 Rev. 0 2998-20356 Rev. 0 2998-20355 Rev. 0 2998-20356 Rev. 0 2998-20355 Rev. 0 2998-1219 Rev. 9 2998-655 Rev. 1 2998-1218 Rev. 9 8770-14084 Rev. 1 8770-14099 Rev. 1 2998-12.18 Rev. 9 2998-1219 Rev. 9 2998-655 Rev. 1 2998-1530 Rev. 5 2998-1218 Rev. 9 2998-1218 Rev. 9

L-2009-069 Page 45 of 49 V3144 FE-3341 V3143 HCV-3646 HCV-3647 V3106 V3206 FCV-3306 FE-3306 V3107 V3207 FCV-3301 FE-3301 SO-03-19 V3427 V3656 SO-03-20 V3414 V3654 V2674 V2501 V2118 V2322 SS-02-1A Suction Stabilizer for CHG PP 2A Pulsation Damper for CHG PP 2A V2169 V2336 V2319 SS-02-1B Suction Stabilizer for CHG PP 2B Pulsation Damper CHG PP 2B V2168 V2464 V2316 SS-02-IC 2998-G-078 Sheet 130B Rev. 28 2998-G-078 Sheet 130A Rev. 19 2998-G-078 Sheet 121A Rev. 31 2998-G-078 Sheet 122 Rev. 25 2998-655 Rev. 1 2998-20097 Rev. 0 2998-1218 Rev. 9 2998-1218 Rev. 9 2998-657 Rev. 2 2998-1024 Rev. 3 2998-4815 Rev. 7 2998-4816 Rev. 6 2998-657 Rev. 2 2998-1024 Rev. 3 2998-4815 Rev. 7 2998-4816 rev. 6 2998-679 Rev. 7 2998-781 Rev.3 2998-679 Rev. 7 2998-780 Rev.3 2998-16238 Rev. 0 2998-3386 Rev. 4 2998-1036 Rev. 1 2998-1033 Rev. 0 2998-7437 Rev. 3 2998-9068 Rev. 5 2998-9067 Rev. 4 2998-9070 Rev. 2 2998-9069 Rev. 2 8770-14084 Rev. 1 8770-14099 Rev. 1 8770-14345 Rev. 1 2998-1033 Rev. 0 2998-7437 Rev. 3 2998-9068 Rev. 5 2998-9067 Rev. 4 2998-9070 Rev. 2 2998-9069 Rev. 2 8770-14084 Rev. 1 8770-14099 Rev. 1 8770-12770 Rev. 1 2998-17048 Rev. 0 2998-1033 Rev. 0 2998-7437 Rev. 3

L-2009-069 Page 46 of 49 Suction Stabilizer for CHG PP 2C Pulsation Damper for CHG PP 2C V2167 V2339 FE-2212 V2429 V2523 V2462 V2535 V2598 V2485 V2433 SE-02-2 V2484 V2432 SE-02-1 V2593 V2515 V2516 V2522 V2341 V2342 (Letdown Heat Exchanger)

LTDN HT EXCH V2347 PCV-2201Q V2349 FE-2202 V2358 2998-9068 Rev. 5 2998-9067 Rev. 4 2998-9070 Rev. 2 2998-9069 Rev. 2 8770-14084 Rev. 1 8770-14099 Rev. 1 2998-1031 Rev. 5 2998-560 Rev. 2 2998-2786 Rev. 5 8770-14084 Rev. 1 8770-14099 Rev. 1 2998-560 Rev. 2 2998-15232 Rev. 3 2998-3487 Rev. 2 2998-1749 Rev. 3 2998-18973 Rev. 0 2998-18974 Rev. 0 2998-19677 Rev. 0 2998-19678 Rev. 0 2998-3487 Rev. 2 2998-1749 Rev. 3 2998-18973 Rev. 0 2998-18974 Rev. 0 2998-19677 Rev. 0 2998-19678 Rev. 0 2998-1009 Rev. 2 2998-548 Rev. 14 2998-548 Rev. 14 2998-2785 Rev. 5 2998-560 Rev. 2 2998-17024 Rev. 0 2998-560 Rev. 2 2998-17023 Rev. 0 2998-1611 Rev. 1 2998-557 Rev. 3 2998-17023 Rev. 0 2998-2586 Rev. 6 2998-4013 Rev. 0 2998-17023 Rev. 0 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-G-078 Sheet 120 Rev. 17

L-2009-069 Page 47 of 49 (Purification Filter)

Purif Filter 2A V2360 V2520 V2359 V2370 (Purification Ion Exchanger)

Purif IX 2A V2378 V2382 V2395 (Letdown Strainer)

S2900 V2415 V2418 V2452 (Purification Filter)

Purif Filter 2B FE-8011 FE-8021 V1442 V 1249 PCV-1I OOF V,1444 V 1477 V1479 V1476 V1478 V1443 2998-19775 Rev. 0 2998-6065 Rev. 3 2998-16332 Rev. 1 2998-5498 Rev. 4 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-2584 Rev. 6 2998-590 Rev. 5 2998-17042 Rev. 1 2998-1029 Rev. 2 2998-3642 Rev. 2 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-17025 Rev. 0 2998-1037 Rev. 1 2998-5064 Rev. 1 2998-17025 Rev. 0 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-1037 Rev. 1 2998-19775 Rev. 0 2998-5498 Rev. 4 2998-6065 Rev. 3 2998-16332 Rev. 1 2998-1420 Rev.6 2998-1421 Rev. 4 2998-2646 Rev. 1 2998-3066 Rev. 5 2998-17056 Rev. 0 2998-187 Rev. 3 2998-546 Rev. 13 2998-3066 Rev. 5 2998-17057 Rev. 0 2998-13278 Rev. 3 2998-13277 Rev. 0 2998-13278 Rev. 3 2998-13277 Rev. 0 2998-3066 Rev. 5 2998-17057 Rev. 0 2998-G-079 Sheet 1, Rev. 41 2998-G-078 Sheet 109 Rev. 18 2998-G-078 Sheet 108 Rev. 5 2998-G-078 Sheet 109 Rev. 18

L-2009-069 Page 48 of 49 PCV-II OOE V1248 Vi1441 FE-01-2 FE-01-1 FE-09-2A FE-09-2B FE-09-2C MV-08-14 MV-08-15 MV-08-16 MV-08-17 V08359 V08360 V09294 V09252 2998-G-078 Sheet 108 Rev. 5 2998-G-080 Sheet 2B Rev.36 2998-G-079 Sheet 1 Rev. 41 2998-G-079 Sheet 2 Rev. 35 2998-G-080 Sheet 2A Rev 43 2998-546 Rev. 13 2998-187 Rev. 3 2998-3066 Rev. 5 2998-17055 Rev. 0 2998-13912 Rev. 1 2998-13912 Rev. 1 2998-2595 Rev. 2 2998-2595 Rev. 2 2998-2595 Rev. 2 2998-10622 Rev. 5 2998-10622 Rev. 5 2998-10621 Rev. 6 2998-10621 Rev. 6 2998-3012 Rev. 8 2998-3012 Rev. 8 2998-2143 Rev. 5 2998-2143 Rev. 5 Table 13 Loop Pressure Drop Distribution Current Primary Geometry AP Geometry AP Friction Station AP Forward Flow Reverse Flow Current Values (p~si)

ý 1~Psuy (P§))~i~j RV Outlet to SG Outlet 26.92 10.88 9.56 SG Outlet to RV Inlet 1.00 3.62 3.62

~EPU Valu~p-z

( psiY (p

1 jjsi)jj (psi)Ži RV Outlet to SG Outlet 33.72 13.64 12.00 SG Outlet to RV Inlet 1.24 4.54 4.54

L-2009-069 Page 49 of 49 Table 14 Heat Balance Information

% EPU Power Feedwater Flow Steam Flow Feedwater Turbine Inlet ibm/hr (2 SG) ibm/hr (2 SG)

Temperature, F Pressure, psia 100 13,345,890 13,247,580 436.2 803.3 90 11,872,120 11,773,810 426.9 711.0 75 9,696,551 9,598,249 410.1 576.4 50 6,223,793 6,125,495 374.6 361.7 25 2,994,037 2,895,675 322.7 190.0 Table 15 RCS Pressure Boundary Material Property Data Material Density Specific Thermal Emissivity Comment (lbm/ft3 )

Heat Conductivity vs Temp (Btu/lbm-F)

(Btuihr-ft-F)

Carbon 483.8*

0.129*

22.92*

0.78-0.82

SA-516 Gr 70 Steel

@130-530

- smooth oxidized C**

iron Stainless 499.4*

0.13*

10.44*

0.57-0.66

304/304L SS Steel

@230-870

- 316 SS repeated C**

heating Inconel 528.8 0.106 8.58 0.85-0.98 600

@480-1090 C Inconel 511.5 0.107 7.75 0.85-0.98 Emissivity assumed 690

@480-1090 C same as Inconel 600

L-2009-069, Submittal of Additional Data for Confirmatory EPU Analyses

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