L-2009-078, Extended Power Uprate Data for NRC Confirmatory EPU Analyses

Extended Power Uprate Data for NRC Confirmatory EPU Analyses

ML091040198
Person / Time
Site:	Saint Lucie
Issue date:	04/02/2009
From:	Katzman E Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2009-078
Download: ML091040198 (94)

Text

0 FPL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 April 2, 2009 L-2009-078 10 CFR 50.4 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 supersedes letter L-2009-069 dated March 23, 2009, that provided additional data requested by the NRC via emails dated May 28, 2008, and December 7, 2008, that is needed to build St. Lucie 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 ESK/KWF/tlt Attachments Aoe -,i an FPL Group company

L-2009-078 Attachment I Page 1 of 44 ST. LUCIE UNIT I EPU Input Data Request to NRC for LOCA Model Item Parameter -Description Units Value Comments No.

1.

Plant Operating Conditions la For rated power conditions (Current)

1. Primary and Secondary Flow rates:

I...**

1. 1. Core flow Unc: +/-14,945 gpm and gpm 410,922 rain flow is 365,000 gpm 1.2. Main coolant pumps 95,000 (IA1I) gpn 96,000 (1A2)

RCP Pump Test Data gpm 95,000 (1 B 1) 94,000 (1B2) 1.3. Steam flow ibm/s See Item I a.7.1 1.4. Feedwater flow lbm/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-2009-078 Page 2 of 44 Item Parameter -Description Units Value Comments No.

2.2. Core inlet Estimate based on Rx S2285 vessel pressure losses of 35.4 psia and core outlet pressure.

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

2.4. Reactor coolant pump discharge Assume a 1 psi pressure psia 2286 drop from RCP discharge to core inlet.

2.5. Steam generator dome Steam Generator Outlet from Benchmarked Heat Balance plus pressure drop to Upstream Outlet Nozzle 2.6. Turbine control valve inlet psia See Item Ila.7.3 2.7. Detailed primary loop pressure drop ps al 4

From Cycle 15 data and distribution ps al 4

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-2009-078 Page 3 of 44 Item Parameter -Description Units Value Comments No.

not have upper head injection.

4.geeaosWater levels in the pressurizer and steam I...

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 percet N/Athe leakage through.guide percent 1.86 tubes (item la.5.5.1). This has not been quantified.

5.4. Upper head to upper plenum (guide pretNAThis has not been

.structure holes) pret/Aquantified.

5.5.bafeCore bypass (guide tubes, barrel-**

1I*I 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-2009-078 Page 4 of 44 Item Parameter -Description Units Value Comments No.

6.

Steam generator recirculation ratio Power-

%Circ~atio See Item I a. 1.5------

7.

Heat balanceinformation, 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 4_Inlet

1.

Plant Operating Conditions lb.

For EPU conditions.

1. Primary and Secondary Flow rates.

'N*@

1. 1. Core flow Nominal value' based on the most recent 9gpm 410,922 measurement. Unc: I 15,000 gpm; TS Min flow is 375,000 gpm 1.2. Main coolant pumps 95,000 (1AI) pm96000 (1A2)

RCP Pump Test Data gpm

.-95,000 (1 B1) 94,000 (1B2) 1.3. Steam flow Ibm/s See Item lb.7.1 1.4. Feedwater flow lbm/hr See Itemlb.7.1 1.5. SG recirculation ratio/boiler section flow Power-Power %Circ Ratio-

% CircRatio 25 14.18

L-2009-078 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 psia 2225

+ 20 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 Ib.7.3 2.7. Detailed primary loop pressure drop psi Table 14 Assumes 10% SG tube distribution plugging.

3.

Primary and Secondary Temperatures:

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

3.2. Cold leg 551 Corresponds to 100%

OF

+/- 3F Power. Tcold at 0% power is 5320F.

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 Reference SG elevations ft 35.0 from bottom of support

L-2009-078 Page 6 of 44 Item Parameter -Description Units Value Comments No.

skirt base. Assumes NWL does not change for EPU.

5. Leakage flows (Bypass):

X 5.1. Outlet nozzle clearances percent 1.27 5.2. Downcomer to upper head percent 0.18 5.3.CEA hrous pecentN/AThis has not been 5.3.CEA hrous pecentN/Aquantified.

5.4. Upper head to upper plenum (guide pretNAThis has not been structure holes) pretNAquantified.

5.5. Core bypass (guide tubes, barrel-5.5.1. Guide tubes Guide and Instrument percent

,2.00 Tu e Tubes 5.5.2. Barrel-baffle Includes Core Shroud percent 0.54 Bps Bypass

6.

Steam generator recirculation ratio Power-See Item Ib.

%CircRatio T. Heat balance information, such as:

W

@*N

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 beelower:

icbe orae of record for LOCA at rated power and Coment See Comment power:

2-9()()

EPU conditions.

Rev. 1, "Exxon Nuclear Company

L-2009-078 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".

• 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-2009-078 Attachment I 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 11

4.

PORV See Table 1I See Table 11 See Table 11

5.

SRV See Table I11 See Table I11 See Table I11

4.

Primary and Secondary Pressure Drops I1. 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 fl~OWS (from design data or vendor analyses).

5.

Core and Fuel Design

1. Number of assemblies N/A 217

2.

Dimensions Ar ray: 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 a

Current values:

4._ Vesselpressuredropsps I

a) 6.8 a) Inlet nozzle & 90 degree

L-2009-078 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 & 1.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 A ssy:......

6. Equipment Drawings and Design Reports and elevations, flow areas, volumes, metal massS and surface areas (including pipe schedules),

L and form loss (due to bends, contractions, expansions, orifices, etc.) for the following

• l equipment I1. Reactor vessel and internals (identification of all core bypass flow paths and flo -w 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).

L-2009-078 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

• l are the same system.

7.

Reactor Vessel Internals l

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 core shroud. Weight includes Tie Rods.

3. Lower core support plate Lbs / sq. ft.

7,900 /243 Includes top and bottom

L-2009-078 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 surfaces; surface areas Lbs Isq. ft.

8,900 / 238 inside the holes of the plate.

5. Upper guide structure Includes CEA shrouds with extensions; total Lbs I sq. ft.

94,400 / 6040 UGS plate, beam, &

s s.

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 Inicludes top and bottom Lbs sq. ft.

3,600 /292 surfaces; surface areas 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 ner Assv

8.

Steam Generator Internals

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

L-2009-078 Attachment I Page 12 of 44 Item Parameter -Description No.

primary side fluid.

1.1. Weight of Tube Sheet 1.2. Area of Tube Sheet (Primary Side)

2.

Weight and surface area of steam generator wrapper.

2.1. Weight of SG wrapper

.tlkbbUI ll~lrXgHlt U1 wrapper Ibm 25,955 is 21.3 ft and material density is 0.284 Ibm/in 3 2.2. Surface area of SG wrapper ft2OuerInner:

84285 Assumei

2.

fheight of wrapper

9.

Steam Generator Fluid Volumes

1. Inlet plenum ft_

222.026 Including Manway

2.

Outlet plenum Wt 222.665 Including Manway

3. Active tubes, Outlet Inactive Tubes, Inlet ft3 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

]

t50.786 ft70.981

10.

Steam Generator Parameters

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

Mass Inventory at EPU bm0 214393 conditions. Recirculation 25 178823 ratios provided in Item lb.

50 160630 1.5 75 147181

L-2009-078 Attachment I 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.

ft2 3.69 per SG Outlet Nozzle Area 2.35 -per SG Flow Venturi Area

12.

Steam Generator and Reactor Vessel

1. Heights J

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 I with internals installed.

13.

Reactor Coolant Pump Rated Conditions

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 13.1 - 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 lbm--t 101,900 polynomial in pump speed)

8. Coolant primary system fluid volume ft3 112 within pump

L-2009-078 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 Strips.

14.

Core Cooling System

1. HPSI and LPSI delivery curves See Tables 12 &

gpm 13 S2.

SIT t Iotal volume Wi 2020

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

/

9 to 1 Nominal liquid volume in

/(1090to1170)

Mode 1.

4.

CST minimum capacity gal 110,000

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

gpm (mimum)

Nominal value does not m(maximum) include 4 gpm for RCP bleed off.

15.a Control Systems Rated power operation of tt heLater secondary control systems for:

I!

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

Iae ae ae

L-2009-078 Attachment I 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 Late

6.

CVCS (charging and letdown)

.Later Later Later 15.b Control Systems EPU condition operation of the primary and,

.. ;ii seodr'control systems for:

a

7.

SG water level instrumentation and control I(heelmn)Later Later Later

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:

core outlet temperature OF Later since the Rx vessel does not have upper head iniectionn

L-2009-078 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 tim e after s c n s31T m o 0 n eto 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 reactivity versus moderator density.

vs z See Tables 7 & 8

4.

Moderator temperature coefficient.

oF vs Ap See Table 9

5. Typical top peaked axial power profile.

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

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

7. Minimum local gap conductance as a fucino TG.Later Later Later function of LHGR.

8.

Gap conductance.

Later Later Later

9.

Linear heat rate.

kW / ft 15.0 (Max)

Value of 6.96 assumes 100

L-2009-078 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-2009-078 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 207F) 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 10 minutes after a MSLB event. Same assumption for EPU analysis.

Most recent COLR provided to NRC via FPL ee Sletter L-2008-244, dated

22.

Core Operating Limits Report See Comment 11-05-2008. 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 OF

L-2009-078 Attachment I Page 19 of 44 Item Parameter -Description Units Value Comments No.

4.

Emissivity versus temperature See Table 16

L-2009-078 Page 20 of 44 Figure 1 PRESSURIZER LEVEL PROGRAM 100.0 80.0 (U

Cd, a-(Uj 60.0 40.0 20.0 0.0 506 522 538 554 570 586 VESSEL AVERAGE TEMPERATURE, TAVE (F) 602

0

-I 9

f.4 99 0

00

L-2009-078 Page 22 of 44 Figure 3 - Location of Fuel Rods and Guide Tubes in Fuel Assemblies CORE IMI4 I

I I

I DE rODS Am. 3-7/85

L-2009-078 Page 23 of 44 A

T

L-2009-078 Page 24 of 44 Table 1 Volume vs. Height for the Reactor Vessel with Internals Installed.

Region Elevation Volume vs. Height Volume (ft)

( ft3 per ft)

(ft3 )

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 V 2, V 3 &

12.8 69.7 892 V4)

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-2009-078 Page 25 of 44 Table 2 Component Data Required Component Flow Diagram Component Information Pressurizer PORVs V1402 8770-G-078 Sheet 110A, Rev 30 8770-9676 Rev 1 V1404 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 I1OA, Rev 30 8770-13730, Rev 1 V 1201 8770-13731, Rev 1 V 1202 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 1 HCV-08-2B 8770-8971, Rev 1 Turbine Control Valves (Governor)

FC-8-4 870G09 he,,Re.4 7013 e

FCV-08-644 I 8770-G-079, Sheet 2, Rev. 45 18770-103, Rev 7

L-2009-078 Page 26 of 44 Component Flow Diagram Component Information FCV-08-645 8770-115,Revll 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.

I 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 11 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-08-1A 8770-G-079, Sheet 1, Rev. 53 8770-9673, Rev 10 HCV-08-IB 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 V21-18 V2623 V2500 V2101 V2322 SS (Suction Stabilizer for Charging Pump 1C)

SS-02-IC CHG PP IC (Charging Pump 1C)

PD (Pulsation 8770-G-078 Sheet 121A Rev. 38 8770-G-078 Sheet 120B Rev 17 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 8770-205 Rev. 0 8770-364 Rev. 4 8770-12137 Rev. 5 8770-12138 Rev. 0 8770-9982 Rev. 1

L-2009-078 Page-27 of 44 Component I Flow Diagram Component Information Damper on CHG PP.1C)

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

V2319 SS-02-IB SS (Suction Stabilizer for Charging Pump 1B)

CHG PP lB (Charging Pump IB)

PD (Pulsation Damper on CHG PP 1B)

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

CHG PP IA (Charging Pump IA)

PD (Pulsation Damper on CHG PP IA)

V2339 8770-9981 Rev. 1 8770-14099 Rev. 1 87.70-14084 Rev. 1 8770-14345 Rev. 1 8770-9379 Rev..1 8770-2310 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. 1 8770-9302 Rev. 5 8770-12137 Rev. 5 8770-205 Rev. 0

.8770-364 Rev. 4 8770-12138 Rev. 0 8770-9982 Rev. 1 8770-9981 Rev. 1 8770-14084 Rev. 1 8770-14099 Rev. 1 8770-14345 Rev. 1 8770-9379. Rev. 1 8770-1592 Rev. 10 8770-9301 Rev. 1 8770-9302 Rev. 5 8770-12137 Rev. 5 8770-364 Rev. 4 8770-12138 Rev. 0 8770-205 Rev. 0 8770-14345 Rev. 1 8770-9378 Rev. 0 8770-10883 Rev. 2 V02132

L-2009-078 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 IA)

V2360 V2520 V2369 V2370 V2378 V2382 V2395 S2900 V2415 V2418' Purif FLTR lB (Purification 8770-G-078 Sheet 120A Rev. 023 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 8770-1578 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-2009-078 Page 29 of 44 Component Flow Diagram I

Component Information Filter IB)

V2452 FE-8011 FE-8021 V09252 V09294 AFW PP IA AFW PP 1B 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 V 1406 V 1407 PZR Quench Tank V1252 V1253 PCV-1 IOOE-PCV-1 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 1 A, 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 8770-125 1, Rev 2 8770-125 1, 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 8770-125 1, 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-2009-078 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 HCV-3616 HCV-3626 HCV-3636 HCV-3646 V3113 V3123 V3133 V3143 FE-3311 FE-3321 FE-3331 FE-3341 HCV-3615 HCV-3625 HCV-3635 HCV-3645 V3114 V3124 V3134 V3144 FE-3312 FE-3322 FE-3332 FE-3342 HCV-3617 HCV-3627 HCV-3637 HCV-3647 V3106 V3107 V3206 V3207 FCV-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 1 FE-3306

L-2009-078 Page 31 of 44 Table 3

L-2009-078 '

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-2009-078 Attachment I Page 33 of 44 Table 5 - Single Phase Homologous Head and Torq ue Curves CURVE 1 CURVE2 CURVE 3 CURVE4 CURVE5 CURVE 6 CURVE7 CURVE 8 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 1085

-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-2009-078 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 11 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 1103B, Rev. 26 8770-39, Rev 3 8770-40, Rev 3 8770-530, Rev 3 8770-781, Rev 3 8770-880, Rev I 8770-1496, Rev 2 Reactor Coolant Pumps 8770-G-078, Sheet II1A, Rev. 15 8770-15, Rev 8 8770-G-078, Sheet 1 IIB, Rev. 15 8770-178, Rev 11 8770-G-078, Sheet 111C, Rev. 14 8770-54, Rev 9 8770-G-078, Sheet 11 ID, Rev. 16 Steam Generators 8770-G-078, Sheet 1 OB, Rev. 26 8770-13348, Rev I 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 1 10A, Rev. 30 8770-G-125 Sheet RC-AB-1, 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-2009-078 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 8770-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 101B, Rev. 26 8770-G-078, Sheet 120A, Rev. 23 8770-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-G-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 1 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-2009-078 Page 36 of 44 8770-B-124 Sheet CH-43 Rev 5 8770-B-124 Sheet CH-63 Rev7.

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 11 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 1 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-i 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-2009-078 Attachment I' 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

(*F)

(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

-0.0186439 No changes from current No changes from current 1077.9

-0.0181490 analysis analysis 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(lbn/ft 3)

-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-2009-078 Page 38 of 44 Table 9. RCS TEMPERATURE vs. MODERATOR REACTIVITY Current Analysis Value EPU Analysis Value RCS MODERATOR RCS MODERATOR TEMPERATURE (°F)

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 (f)***(*)

____t__*___****__

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-2009-078 Page 39 of 44 Table 11 - PSL Unit-1 RPS, ESFAS and AFAS Setpoints and Safety A alysis 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 > 11 IIF but < 2000F.

RPS S/G Level Lo 21.0%

Ž20.5%

+/- 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) 140 psi (Normal)

+/- 80 psi (Accident)

+ 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 definedas Contaimnent.

Temperature > 11 l°F but < 2000F.

RAS RWT Level Lo 48 inches

.. 48 inches

+/- 6 inches

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

Ž19.0%

+/- 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 "L 160 psi (Worst Normal)

Temperature > 11 1°F but < 200'F.

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 13% (tolerance)

PZR Safety RV N/A 2500 psia (nominal)

+ 3%, - 2.5% (tolerance)

+ 3%, - 2.5% (tolerance) 7 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-2009-078 Page 40 of 44 TABLE 12 ST. LUCIE UNIT 1 - HIGH PRESSURE SAFETY INJECTION PUMP DELIVERY FLOW/PUMP DEGRADED PUMP I NON-DEGRADED PUMP NOMINAL MINIMUM NOMINAL MAXIMUM I

4-LOOP 34_OOP RCS 4-LOOP HIGHEST 4-LOOP 34-O(CP PRESSUR 4TOTAL MINIMUM PRESSURE TOTAL 3-LOOPS TOTAL MAXIMIVUM PRESSRE TOTAL 3-LOOPS SIS PRESSLRE TANALYSIS

• MIN ANALYSIS MAX AAYI (psia)

(gpm)

(gpm)

(gpm)

(gpm)

(psia)

(gpm)

(gpm)

(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-2009-078 Page 41 of 44 Table 13. ST. LUCIE UNIT 1 -

LOW PRESSURE SAFETY INJECTION PUMP DELIVERED FLOW Min Degraded LPSI Flow/Pump (4 Valves)

I Max LPSI FlowlPump (4 Valves)

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

(GPM)

(G.PM) 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

ý73.31 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 71V3 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 I

Each LPSI and HPSI providesinjection flow to all four legs.

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

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

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

L-2009-078 Page 42 of 44 Table 14 Primary Loop Pressure Drop Distribution Geometry AP Geometry AP Friction Forward Reverse Flow Reference #

Station AP Flow_"

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 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 75L4 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-2009-078 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-2009-078 Page 44 of 44 Appendix A - Calculation of Fuel Assembly Grid Weight and Surface Area

.L-2009-078 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 1

For rated power conditionsa.

1. (Current):

1. Primary and Secondary Flow

.. =* **; ** '*,<,, **

i rates:

1. 1. Core flow g

4200 Unc: + 14,500 gpm and gpm 42,000 min flow is 335,000.

1.2. Main coolant pumps 97,500 (2A1) m

.P96,000 (2A2)

RCP Pump Test Data 95,000 (2B1) 94,000 (2B2) 1.3. Steam flow Ibm/hr See Item Ia 7.1 1.4. Feedwater flow lbm/hr See Item la 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:

• i*

2..Pesrze*sa25 Nominal Operating I

rsuie sa25 Pressure is 2250 psia.

L-2009-078 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 1 psi pressure discharge psia 2287 drop from RCP discharge to core inlet.

2.5. Steam generator dome SG outlet pressure from 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 siAssumes 10% SG tube pressure drop distribution pplugging.

3.

Primary and Secondary Tem peratures:

i

3. 1. Hot leg Assumed to be the same as the core outlet OF 600 temperature 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 Based on Tcold of 549F and Tave of 574.5F.

L-2009-078 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 inection.

4.

Water" levels in the pressurizer NN**

and steam generators, 42StaGeeaosin 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 1.12 breakdown documented in Unit 1 UFSAR due to unit similarities.

5.2. Downcomer to upper head Assume bypass 0.16 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 la.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 cauantified.

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

L-2009-078 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 pecnt04 breakdown documented percen 0.47in Unit I UFSAR due to unit similarities.

6.

Steam generator recirculation Power-rtoSee Item la 1.5 ratio%CircRatio

7.

Heat balance information such 7.1. Feed and steam flows lbm/hr 11,905,010 Benchmark Heat 11,806,740 Balance 7.2. Feedwater temperature

°F*45Benchmark Heat Balance 7.3. Turbine inlet pressure.

Benchmark Heat psia "85'2.7 Balance, Turbine Inlet

~Valve

1.

Plant Operating, Conditions N

lb.

For EPU conditions.

1. Primary and Secondary Flow.

rates:

1. 1. Core flow Minimum flow is gpm 412,000 375,000 gpm.

1.2. Reaictor coolant pumps 97,500 (2A1) gpm 9,00(A)

RCP Pump Test Data

.,95,000 (2131) 94,000 (2B2) 1.3. Steam flow lbmn/s See Item'lb 7.1

L-2009-078 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

%CircRatio 50 7.06 75 4.40 100 3.02

2.

Primary and Secondary Pressures (absolute pressures):

4 g

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

Uric.: + 45 psi normal,

+ 90 psi 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 895.8 heat balance plus dP to upstream of flow restrictor extrapolated using EPU flow 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 plugging.

distribution

3. Primary and Secondary

L-2009-078 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%

Power. Tcold at zero power is 532F.

• 3.3 Core outlet

F679Assumes 10% SG tube OF 607.9plugging.

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

4 Water levels in the pressurizer and steam generators pa

__4.1 Pressurizer

% Tap Span See Figure I below 4.2 Steam Generators in 411.3 Level above tubesheet 5 Leakage flows:,

% of vessel 37----

flow

.5.1 AOutlet nozzle clearances pecn

.2Assumed to be similar to current operating value.

5.2 C t uper ead ercnt

.16Assumed to be similar to 5.2 C t uper ead ercnt

.16current operating value.

5.3 CEA shrouds pretNAThis has not been quantified.

5.4 Upper head to upper plenum p retNAThis has not been (guide structure holes) quantitied.

5.5 Corebarlbafebypass (guide tubes, t...

5..1 GudetuesAssumed to be similar to 5.. ud ue*percent 1.76 c Iurrent operating value.

5.5.2 Barrel-baffle

-ecnt04 Assumed to be similar to current operating value.

6 Steam generator recirculation Power-Se tm l ratio

%CircRatio

L-2009-078 Page 7 of 49 Item Parameter -Description Units Vain Comments No.

7Heatas balance information such 7.1 Feedwater and steam flows lbm/hr See Table 14 7.2 Feedwater temperature OF See Table 14 7.3 Turbine inlet pressure,.si See Table 14

2.

Analysis Topical Reports See References provided below applicable to rated power:

• CENPD-132, through Suppl. 4-P-A, "Calculative Method for the CE Nuclear Power Large Break LOCA I. Topical Report on the Evaluation Model",

March 2001.

licensn analysise of record See See Comment o

CENPD-137, for LOCA at rated power and Comment 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-2009-078 Page 8 of 49 Item Parameter -Description Units Value Comments No.

and Delay Times Critical Safety Parameters List (also called "Groundrules document") for the last reload I1. 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 NN N @!*

Pressure Drops

&*1 I1. 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 Desi -gn',

• 2 S1.

Number of assemblies l

N/A 217 1i2.

Dimensions N/A Array: 16 x 16, The pitch is the sum of SPitch:

8.180 in, 7.972 and 0.208 = 8.180

L-2009-078 Page 9 of 49 Item Parameter -Description Units Value Comments No.

Length: 158.5 in in.

3.

Spacer grid locations and K-See Table 4 for Spacer grid K-factors to factors N/A grid locations, be provided later.

4.

Vessel pressure drops Current values:

a) Inlet nozzle & 90 degree turn, Sa) 5.0 b) Downcomer, lower psi b) 10.4 plenum, support c) 13.4 structure, 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-2009-078 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 See Table 3 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-2009-078 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

7.

Reactor Vessel Internals Weight and surface area of N

}

reactor vessel internal structures:

8. Core support barrel Includes upper, center, 136,600/ I and lower portions of the Lbs / sq. ft.

1126 Inside core support barrel I 110 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.

9,900/331 surfaces; surface areas inside the holes of the plate.

12. Upper guide structure Includes CEA shrouds with extensions; total Lbs Isq. ft.

120,000 / 7,120 UGS plate, flange, beam,

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

L-2009-078 Page 12 of 49 Item Parameter -Description Units Value Comments No.

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

45,500 / 11 93 flanges; cylinder; 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 2100 outside shroud extensions.

16. Shroud extensions 10,400/

Lbs /sq. ft.

866 Inside 105outside

17. G rid assemblies Lbs /sq. ft.

18. - / 5.0 per Grid Each assembly has 9

.grids for 217 assemblies.

8.

Steam Generator Internals sheet and surface area of tube SE 1.Wih fside)m fteatrtue 2

72**

.29.stmatd.ro sheet exposed to primary side fluid.

1. 1. Weight of.Tube Sheet Weight with integral ibm 93,230 forged lower cylindrical

~ring and cladding 1.2. Surface area of Tube Sheet PRELIMINARY (Primary Side)*"

ft2 72.29 Estimated from I tubesheet OD minus 2X I

-tube OD

2.

Weight and surface area of steam generator wrapper.

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

L-2009-078 Page 13 of 49

5. Length of shortest and longest in Single straight leg (not including tubesheet) 262.598 min 273.425 max Tube bend radius (to tube centerline) 4.134 min 73.134 max

10.

Steam Generator Parameters

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

Ibm Power Secondary Mass 0

215680 25 184560 50 164650 75 150600 100 139430 Inventory at EPU, conditions. Recirculation ratios provided in Item lb. 1.5

L-2009-078 Page 14 of 49 Item Parameter -Description Units Value Comments No.

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 t2"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 downcomner 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

• 1.

Reactorconitonsolant Pump Rated

1. Conditions

1.

Head The value is the average ft 26.75 of the four pump-specific

~values (303, 296, 293 &

~295 ft)

2. Flow gpm 87,750 The value is the average

L-2009-078 Page 15.of 49 Item Parameter -Description Units Value Comments No.

of the four pump-specific values (85,000 - 87,500 -

91,000 & 87,500 gpm)

3.

Torque The value is the average of the four pump-specific lbf-ft 33,950 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! ft' 4of the four pump-specific values (47.3, 47.4, 46.9 and 48.4 Ibm/! 3 W)

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)

.Ilbm-f 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),

20 (max)

L-2009-078 Page 16 of 49 Item Parameter -Description Units Value Comments No.

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 Itrips.

14.

Core Cooling System

1. HPSI and LPSI delivery curves g

See Tables 8, 9, 10,

2.

SIT total Volumne Wt 1855 Four tanks, each with this capacity.

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

TS ranges for SIT volume W

(1420to 1556 +

pressure and liquid

32) volume.

4.

CST minimum capacity gal 276,200

5. Charging pump flow versus Reciprocal pump. Flow pressure40 (nominal) to 49 is per charging pump.

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

15.a Control Systems primary and secondary control systems for:

lI

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

5. Auxiliary feedwater Later Later Later

L-2009-078 Page 17 of 49 Item Parameter -Description Units Value omments No.

6. CVCS (charging aind letdbwn)

Later Later

-Later 15.b Control Systems W

EPU condition operation of the primary andhsecondary control Lt Lae ae systems for:

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

8. SG pressure (incluiding 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 VesselUpper 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:

Later Ixssumiie Lt Oe ULIM saitie as the core outlet temperature since the Rx vessel does not have

L-2009-078 Page 18 of 49 Item Parameter -Description Units Value Comments No.

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 v.ersus tim e LaeL t rL t r 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

7.

Minimum local gap conductance Later Later Later

L-2009-078 Page 19 of 49 Item Parameter -Description Units Value Comments No.

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 burnup for the hot rod in the hot bundle.

21.

Operator Actions During

2. LOCA

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 Non a

LOP 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:

See Comments

• RCS subcooling is Section.

greater than or equal to minimum subcooling

• Pressurizer level is at least 30%

and NOT lowering,

_ At least ONE S/G is

L-2009-078 Page 20 of 49 Item Parameter -Description Units Value Comments No.

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-2009-078 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 i*lI i

steel, inconel, etc.):

1. Density lb/ft3 See Table 15

2.

Specific heat BTU/ lbm-0 F See Table 15

3.

Thermal conductivity BTU/hr-ft- 0F See Table 15

2.

Emissivity versus temperature See Table 15

L-2009-078 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 4 55 I CL (U

-j w

cc, IL 50 1 45 1 40 +

35 1 (538.2, 33.1) 30 1 25 !

520 I

I I

I

.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-2009-078 Page 23 of 49 Figure 2 - RCP

. Coastdown -

10.

12 ST.

Co Lr aLve FbU 51 Note: Curve represents current analyses.

L-2009-078 Page 24 of 49 Figure 3

L-2009-078 Page 25 of 49

.Figure 4

L-2009-078 Page 26 of 49 Table 1 (Later)

L-2009-078 Page 27 of 49 Table 2 (Later)

L-2009-078 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. 1 2998-1887, Rev. 3 299841886, Rev. 6 Reactor Coolant Pumps 2998-G-078, Sheet II1A, Rev. 11 2998-455, Rev. 6 2998-G-078, Sheet 11 B, Rev. 10 2998-457, Rev. 8 2998-G-078, Sheet 11 IC, Rev. 13 2998-G-078, Sheet 11 ID, Rev. 10 Steam Generators 2998-G-078, Sheet 110, Rev. 8 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-125, 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-2009-078 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 2998-6-125, 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-1, 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 CH-G-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-110, Rev. 14 2998-C-124, Sheet CH-111, Rev. 11 2998-C-124, Sheet CH-I 12, Rev. 13 2998-C-124, Sheet CH-129, Rev. 0 2998-C-124, Sheet RC-2, Rev. 13

L-2009-078 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-2009-078 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)

+ 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)

40 psi (Normal)

+/- 80 psi (Accident)

+ 80 psi (Accident)

RPS S/G Level Lo 20.5%

> 20.5%

+/- 5% (Normal)

+ 5% (Normal)

+/- 14% (Accident)

+/- 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)

+/- 90 psi (Accident)

MSIS S/G Press Lo 600 psia

> 600 psia

+/- 40 psi (Normal)

+/- 40 psi (Normal)

+/- 80 psi (Accident)

+/- 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)

A 5% (Normal)

A: 14% (Accident)

A 14% (Accident)

AFAS S/G Press DP Hi 270 psid

< 275 psid Not specified A: 60 psi (Normal)

A: 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)

A: 3% (Bank 1 tolerance)

A: 3% (Bank I tolerance) 1040 psia (nominal)

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

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

3% (accumulation) 3% (accumulation)

PZR Safety RV N/A 2500 psia (nominal)

+/- 3% (tolerance)

+/- 3% (tolerance) 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-2009-078 Page 32 of 49 Table 6 or Coolant Pu, Line

• L-2009-078 Page 33 of 49

L-2009-078 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

-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-2009-078 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)

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 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-2009-078 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 01 279

L-2009-078 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 0

1535

L-2009-078 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 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-2009-078 Page 39 of 49 Table 10 SL-2 SAFETY INJECTION DATA NO FAILURE IN ECCS EFFECTIVE FOR NON-LOCA ANALYSIS (All Pumps On)

MINIMUM RCS Flow to RCS Flow to Pressure Loop Al, A2.

Pressure Loop Al, 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-2009-078 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-2009-078 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) 1B2 (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-2009-078 Page 42 of 49 Table 12 Component Data Required Component Flow Diagram Component Information Pressurizer PORVs V1474 2998-G-078 Sheet 108 Rev. 5 2998-18810 Rev. 3 V1475 I

I Pressurizer Safety Valves V1200 2998-G-078 Sheet 109 R18 2998-19690 Rev. 1 V1201 2998-19691 Rev. 1 V1202 I

I 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 V8211 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 FCV-08-642 2998-G-079 Sheet 2, Rev.35 2998-2184 Rev. 10 2998-31, Rev 17

L-2009-078 Page 43 of 49 FCV-08-643 I

I Main Feed Isolation Valves HCV-09-1A 2998-G-080 Sheet 2A Rev. 43 2998-9486 Rev. 4 HCV-09-1B 2998-9487 Rev. 4 HCV-09-2A HCV-09-2B Main Steam Isolation Valves HCV-08-1A 2998-G-079 Sheet 1, Rev. 41 2998-1011 Rev. 3 Sheet 1/9 HCV-08-1B 2998-1012 Rev. 0 Sheet 2/9 Miscellaneous Components V09107 V09108 SE-09-2 2998-G-080 Sheet 2B Rev.36 MV-09-9 V09119 V09120 V09123 V09124 SE-09-3 MV-09-10 V09135 V09136 V09139 V09140 SE-09-4 MV-09-11 V09151 V09152 SE-09-5 MV-09-12 V09157 V09158 2998-20110 Rev. 1 2998-741 Rev. 3 2998-13008 Rev. 3 2998-13006 Rev. 1 2998-13009 Rev. 2 2998-19745 Rev. 2 2998-1872 Rev. 6 2998-5616 Rev. 0 2998-3033 Rev. 4.

2998-742 Rev. 2 2998-20110 Rev. 1 2998-741 Rev. 3 2998-13008 Rev. 3 2998-13006 Rev. 1 2998-13009 Rev. 2 2998-19745 Rev. 2 2998-1872 Rev. 6 2998-5617 Rev. 0 2998-3033 Rev. 4 2998-742 Rev. 2.

2998-752 Rev. 5 2998-751 Rev. 2 2998-13007 Rev. 1 2998-13008 Rev.3 2998-13009 Rev. 2 2998-19745 Rev. 2.

2998-1871 Rev. 7 2998-5617 Rev. 0-2998-3033 Rev. 4 2998-742 Rev. 2 2998-13007 Rev. 1 2998-13008 Rev.3 2998-13009 Rev. 2 2998-19745 Rev. 2 2998-1871 Rev. 7 2998-5616 Rev. 0 2998-3033 Rev. 4 2998-742 Rev. 2

L-2009-078 Page 44 of 49 V3225 V3624 V3258 V3227 V3215 V3614 V3259 V3217 V3245 V3644 V3261 V3247 V3235 V3634 V3260 V3237 FE-3312 HCV-3615 V3114 V3805 FE-33111 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 V3144 2998-G-078 Sheet 132 Rev. 9 2998-G-078 Sheet 131 Rev. 20 2998-19174 Rev. 2 2998-4353 Rev. 5 2998-784 Rev.A6 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 o 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 2998-1218 Rev. 9 2998-1219 Rev. 9 2998-655 Rev. 1 2998-1530 Rev. 5 2998-1218 Rev. 9 2998-1218 Rev. 9 2998-655 Rev. 1

L-2009-078 Page 45 of 49 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-IB Suction Stabilizer for CHG PP 2B Pulsation Damper CHG PP 2B V2168 V2464 V2316 SS-02-IC Suction 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 2998-20097 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 2998-906 9 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 2998-9068 Rev. 5

.L-2009-078 Page 46 of 49 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 (Purification 2998-9067 Rev. 4, 2998-9070 Rev. 2 2998-9069 Rev. 2 81 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 2998-19775 Rev. 0 2998-G-078 Sheet 120 Rev. 17

L-2009-078 Page 47 of 49 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 V 1442 V 1249 PCV-1 IOOF V 1444 V 1477 V 1479 V1476 V1478 V1443 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. ]

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 2998-546 Rev. 13 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 PCV-1 IOOE

L-2009-078 Page 48 of 49 V 1248 V1441 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 2998-187 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 Current Primary Loop Pressure Drop Distribution Geometry AP Geometry AP Friction Station AP Forward Flow Reverse Flow CurenVlusps__s_)

(psi)

RV Outlet to SG Outlet 26.92 10.88 9.56 SG Outlet to RV Inlet 1.00 3.62 3.62 tEPU Values (psi___

_4)______

RV Outlet to SG Outlet 33.72 13.64 12.00 SG Outlet to RV Inlet 1.24 4.54 4:54

L-2009-078 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)

(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