L-2008-266, Data for NRC Confirmatory EPU Analyses

Data for NRC Confirmatory EPU Analyses

ML083657355
Person / Time
Site:	Saint Lucie
Issue date:	12/23/2008
From:	Katzman E Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2008-266
Download: ML083657355 (89)

Text

0 Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 December 23, 2008 FPL L-2008-266 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-2008-262 dated 12/18/2008 that provided additional data requested by the NRC 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 Attachments A-Je(

an FPL Group company

. L-2008-266 Attachaent 1 Page 1 of 42 ST. LUCIE UNIT 1 EPU Input Data Request to NRC for LOCA Model Item Parameter -Description Units Value Reference Comments No.

1. Plant Operating Conditions la For rated power conditions (Current)

1. Primary and Secondary Flow rates: t*****i* *=**'g"*l I. . or fowgpm 410,922 Ref. 4, Item 1.6.29 n:1,4gptad min flow is 365,000 gpm 1.2. Main coolant pumps 95,000 (1A1) gpn96,000 (1A2) Ref. 8, Table 2 RCP Pump Test Data gpm 95,000 (1B1) 94,000 (1B2) 1.3. Steam flow lbm/s See Item Ia.7.1 1.4. Feedwater flow Ibm/hr See Item Ila.7.1---------

1.5 SG recirculation ratio/boiler section Power %Circ flow Ratio Power- 25 15.3 Reference 11, 50 8.7 Figure 6.3

% CircRatio 75 5.95 90 4.9 1AA A I

2. Primary and Secondary Pressures:

2.1. Pressurizer vressure range is zz2l to 2275, with Unc: +/- 22 Normal, + 80 Accident 2.2. Core inlet Estimate based on Rx vessel pressure losses of 35.4 psia and core outlet

L-2008-266 Attachment 1 Page 2 of 42 Item Parameter -Description Units Value Reference Comments No.

pressure.

2.3. Core outlet Assumed to be the same as psia 2250 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 Reference 9 Steam Generator Outlet psia 861.5 Reference 11, from Benchmarked Heat Figur 10.5to Upstream Balance pressure plus Outlet drop Nozzle 2 .6 . Tu r b in e c o n tr o l v a lv e in let pi e t ml . . ----- ---

2.7. Detailed primary loop pressure drop piTbe1 Rf29From Cycle 15 data and 0% SG tube plugging.

3. Primary and Secondary Temp549tuco:teper **aturtsl 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 Ref. 8, Item 6. Tcold temperature at full Unc: +/- 3°F power.

3.3. C ore outlet OF5 9Current PI Process ----

data.

• 3.4. Upper Head Assumed to be the same as the core outlet temperature OF 599 ----- since the Rx vessel does not have upper head injection.

L-2008-266 Attachment I Page 3 of 42 Item Parameter -Description Units Value Reference Comments No.T

4. Water levels in the pressurizer and steam t1 ' . ..  ! I i".....*I **

generators. IN 4 . 1. P ressurizer %T p S aS e Fi u e 1 R ef. 8, Attachm ent ----

% Ta SpaSeeFigue 1 1, Figure 3.

4.2. Steam Generators Reference SG elevations ft 35.0 Ref. II from bottom of support skirt base.

5. Leakage flows (Bypass):  % of vessel 3.9 Ref.8, Item 10.

flow 5.1. Outlet nozzle clearances Ref. 1, Table 4.4-3, percent 1.18 ti. 2.

Item 5.2. Downcomer to upper head Ref. 1, Table 4.4-3, percent 0.17 IesI&6 Itemns I & 6.

5.3. CEA shrouds Equivalent to a fraction of percent N/A Ref. 1, Table 4.4-3 the leakage through guide tubes (item la.5.5.l). This has not been quantified.

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

baffle)bypass (guide tubes, barrel-..

5.5. Core . . . . . .... . .. .... . . . ... ... .

5.5.1. Guide tubes Ref. 1, Table 4.4-3, percent 1.86 Item 5 (HVFR fuel assemblies not used).

5.5.2. Barrel-baffle Ref.1, Table 4.4-3, Items 3 and 4.

6. Steam generator recirculation ratio Power-See Item la. 1.5

%CircRatio

7. Heat balance information, such as:

L-2008-266 Attachmnent I Page 4 of 42 Item Parameter -Description Units Value Reference Comments No.

7.1. Feedwater and steam flows Jbmir 11,851,050 Reference 9 Benchrmarked Heat 11,784,590 Balance 7.2. Feedwater temperature OF 435 Reference 9 Benchmarked Heat Balance 7.3. Turbine inlet pressure Benchmarked Heat psia 816.4 Reference 9 Balance, Turbine Valve Inlet lb. For EPU conditions.

1. Primary and Secondary Flow rates: i*N N N iiiil*,

I.1I. Core flow Nominal value based on the most recent gpmn 410,922 Ref. 4, Item 1.6.29 measurement. Unc:+

15,000 gpm; TS Min flow is 375,000 gpm 1.2. Main coolant pumps 95,000 (IAI) gpM 96,000 (1A2) Ref. 3, Attach#], RCP Pump Test Data 95,000 (1B1) Page 17 of 41.

94,000 (1B2) 1.3. Steam flow Ibm/s See Item lb.7.1 1.4. Feedwater flow Ibm/hr See Item lb.7.1 1:5. SG recirculation ratio/boiler section flow Power-Later Later Later

% CircRatio

2. Primary and Secondary Pressures:

2. 1 Presurzer sia2225 to 2275 Ref. 4, Item 1.6.31 ----

2.1. Pressurizer 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.

L-2008-266 Attachment 1 Paae 5 of 42 Item Parameter -Description Units Value Reference Comments No.

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

2.5. Steam generator dome psia Later Later Later 2.6. Turbine control valve inlet psia See Item lb.7.3 2.7. Detailed primary loop pressure drop psi Table 14 Ref. 27 Assumes 10% SG tube distribution plugging.

3. Primary and Secondary Temperatures:

3.1. Hot leg OF 606.0 Ref 28 Assumes 10% SG tube plugging.

551 Ref. 4, Page 17 of Corresponds to 100%

3. llOF 551 3F Ref. Pae Power. Tcold at 0%power is 532nF.

3.3. Core outlet cF 608.2 Ref. 28 Assumes 10% SG tube plugging.

3.4. Upper Head pF 608.2 Ref, 28 Assumed to be the same as vessel outlet.

4. Water levels in the pressurizer and steam l '*~**

generators. L 60!

4.1. Pressurizer  % Tap Span See Figure I F gRef3,A t c .I- ---

4.2. Steam Generators Reference SG elevations of from bottom of support 29 3, Page 10 Ref. skirt base. Assumes NWL

-does not change for EPU.

5. Leakage flows (Bypass): * * **!:*1 **"

5. 1. Outlet nozzle clearances percent 1.27 Ref. 4, Sec. 1.6. ----

5.2. Downcomer to upper head percent 0.18 Ref. 4, Sec. 1.6. ----

5.3.CEAshrudspercnt 5.3.CEAshruds ercnt /A

/A ------ This has not been uantified.

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

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

L-2008-266 Attachment I Page 6 of 42 Item Parameter -Description Units Value Reference Comments No. 5.5.. Gude tbesGuide and Instrument 5.5.1. Guide tubes percent 2.00 Ref. 4, Sec. 1.6. Tubes Includes Core Shroud 5.5.2. Barrel-baffle percent 0.54 Ref. 4, Sec. 1.6. Bypass

6. Steam generator recirculation ratio Power- See Item Ib.

%CircRatio

7. Heat balance information, such as:

7.1. Feedwater and steam flows lbmihr Later Later Will be provided when finalized 7.2. Feedwater temperature OF Later Later Will be provided when finalized 7.3. Turbine inlet pressure, psia Later Later Winllizeprvdedwe

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

XN-NF-82-49(P)(A),

Rev. 1, "Exxon Nuclear Company Evaluation Model

1. Topical Report on the licensing analysis Revised EXEM PWR of record for LOCA at rated power and See See Comment See Comment Small Break Model",

Comment EMF-2328(P)(A),

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

• EMF-2087(P)(A),

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

L-2008-266 Attachment 1 Page 7 of 42 Item Parameter -Description Units Value _ Reference Comments No.

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

4. rTimes Critical Safety Parameters List (also called "Groundrules document") for the last reload fo r:

I !. ESFAS See Table I11 See Table 11 See Table I1I See Table II i2. RPS See Table II See Table I11 See Table I11 See Table 11 i.3. SGIS/MSIS See Table I11 See Table I1I See Table I11 See Table I11

4. PORV See Table I11 See Table I11 See Table II See Table 11

5. SRV See Table I11 See Table I11 See Table I11 See Table I11

4. Primary and Secondary Pressure Drops ** *, *,i! *....

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

2. Secondary side pressure drop distribution Later Later Later Later

L-2008-266 Attachmnent I Page 8 of 42 Item Parameter -Description Units Value Reference Comments No.

with corresponding flow rate, including leakage flows (from design data or vendor analyses).

5. Core and Fuel Design

1. Number of assemblies N/A 217 Ref. 1, Table 4.2- 10 ----

2. Dimensions Array: 14 x 14, N/A Pitch: 8.18 in, Ref 1, Table 4.2 -10 ----

Length: 157.115 in

3. Spacer grid locations and K-factors K-factors See Table 4 for Core inlet region/ bottom Grid locations. Ref. 26 grid = 3.530 N/A Mid-grid 7 spacers = 8.496 See Comments for Ref. 12 Outlet region/top grid =

K-factors. 4.63 Bare rod = 3.971

4. Vessel pressure drops Current values:

a) Inlet nozzle & 90 degree a) 6.8 turn, psi b) 21.5 Ref 1, Table 4.4-4 b) Downcomer, lower c) 2.1. plenum, support structure c) 7.1 &fuel assembly, c) Fuel assembly outlet to outlet nozzle.

5. Bypass and leakage flows  % of total See Comment See items la.5.5 & See items la.5.5 & 1.b.5.5 flow 1.b.5.5 above above

6. Number and location of fuel rods N/A 176 per Assy. Ref. 1, Table 4.2-10 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 Ref. 1, Table 4.2-10 See Figure 3 for location.

6. Equipment Drawings and Design Reports

L-2008-266 Attachment I Page 9 of 42 Item Parameter -Description Units Value Reference Comments No.

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 equipment:

1. 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).

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 --- See Table 6 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.

L-2008-266 Attachment 1 Page 10 of 42 Item Parameter -Description Units Value Reference Comments No. ý

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

1. Core support barrel tncluaes upper, center, anci 103,500/ lower portions of the core Lbs / sq. ft. 1046 Inside Ref. 30 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 Ref. 30 horizontal surfaces of the 865 outside core shroud. Weight includes Tie Rods.

3. Lower core support plate Includes top and bottom surfaces; surface areas Lbs / sq. ft. 7,900 / 243 Ref. 30 inside the holes of the plate.

4. Fuel alignment plate (Upper Core Plate) Includes top and bottom Lbs / sq. ft. 8,900/238 Ref. 30 surfaces; surface areas inside the holes of the plate.

5. Upper guide structure Includes CEA shrouds with extensions; total Lbs / sq. ft. 94,400 / 6040 Ref. 30 cyln eraeas; t cylinder areas; total fuel

' alignment plate area Neglects guide tubes).

6. Core support assembly Includes vertical webs; Lbs / sq. ft. 47,800 /1371 Ref. 30 flanges; cylinder; columns core support plate (Item 3 above); bottom plate.

7. Flow skirt Includes top and bottom Lbs / sq. ft. 3,600/292 Ref. 30 surfaces; surface areas inside the holes of the plate.

L-2008-266 Attachment I Pane 11 of 42 Item Parameter -Description Units Value Reference Comments No.

8. Control element assembly (CEA) shroud 41,300/ Includes single and double Lbs / sq. ft. 1980 Inside Ref. 30 shrouds.

2167 outside

9. Shroud extensions 3,000 / Includes single and double Lbs / sq. ft. 386 Inside Ref. 30 shrouds.

476 outside

10. Grid assemblies Lbs /sq. ft. 20.60 / 71.2892 Appendix A

8. Steam Generator Internals

1. Weight surface of steam area Fumes generator of tube s to and sheet exposed " ***e primary side fluid.

1f cld sb emta

1. 1. Weight of Tube Sheet Inldsbemta lbm 94,334 Ref. 3, Items B1.38 and 61 (93,239 lbm) and cladding (1095 lbm).

1.2. Area of Tube Sheet (Primary Side) ft2 75 Ref 3, Item B 1.42 Area for tube sheet only.

2. wrap Weight andsurface areaofsteam generatortus/8 p er.

Rf 3Atah#

• l R J&:t*!* * *~

2. 1. Weight of SG wrapper Ref. 4, Item 1.12.35, Assume height of wrapper

-Ibm 25,955 36, and 37. Also, is 21.3 ft and material Ref. 21 densim is.1284.35,n 2.2. Surface area of SG wrapper ft2 Inner: 842 ande3. Itemf.1235 A4s, Assume height of wrapper Outer: 850 an271 lsRf is 21.3 ft.

9. Steam Generator Fluid Volumes **,',, , ** , ,*** * **,*

1. Inlet plenum Wt 222.026 IRef. 3, Item B1. 1 IIncluding Manway

2. Outlet plenum Wt 222.665 Ref. 3, Item B 1.6 Including Manway

3. Active tubes, Outlet Inactive Tubes, Inlet Wt 1129.04 (Active), Ref. 3, Items B 1.4, Inactive Tubes 36.635 (Outlet)', 1ad5.----

36.635 (Inlet) 3,nd5

4. Number of steam generator tubes N/A 8523 Ref. 3, Attach # 1, ----

L-2008-266 Attachment I Pane 12 of 42 Item Parameter -Description Units Value Reference Comments No.

Item 43.

5. Length of shortest and longest tubes __ _50.786 Ref. 24 --------

70,981 ----

10. Steam Generator Parameters

1. Inventory and recirculation ratio versus loadLaeL trL trL tr (essential at rated power conditions). Ltr ae ae ae

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

11. MS Line Flow Restrictor "

1. Restrictor flow area. ft: 3.69 per SG Ref. 3, Section Outlet Nozzle Area 12.35 per SG B6. 1.10 and 11. Flow Venturi Area Steam Generator and Reactor Vessel

12. 1.Heights -

1. Volume versus height relationship for the Steam generators, with downcomer and ft3 VS. ft See Table 3 Ref 11 ----

boiler regions provided separately.

2. Volume versus height for the reactor vessel Ref 1, Tables 4.4-with internals installed. ft3 vs. ft See Table 1 4B, 4.4-4C, and t* I ~Figure 4.4-21 I /

13. Reactor Coolant Pump Rated Conditions

1. Head ft 273.5 Ref. 4, Item 1.9.22 ----

12. Flow gMi 95,000 Ref. 4, Item 1.9.21 ----

3. Torque lbf-ft 32,750 Ref. 4, Item 1.9.25

4. Speed rpm 886.25 Ref 4, Item 1.9.24

5. Density lbs/ft3 Later

6. Homologous pump curves (four quadrant) N/A See Table 5 Ref. 4, Table 4

7. Pump inertia and fiiction (coefficients of Ibm-ft2 101,900 Ref. 4, Item 1.9.23 polynomial in pump speed) I I

L-2008-266 Attachment I Page 13 of 42 Item Parameter -Description Units Value Reference Comments No.

8. Coolant primary system fluid volume ft3 112 Ref. 4, Item 1.9.29 within pump

9. RCP metal mass, excluding motor lbs 75,000 Ref. 16 Dry Weight

10. Reverse rotation device operational for N/A Yes Ref. 4, Item 1.9.26 Device prevents reverse RCPs rotation.

11. Pump power to primary fluid 14.6 MWt MW (nominal), Item 1.15.13 20 MWt (max)

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

13. Pump trip setpoints N/A Overcurrent Ref. 17 Overload Trip.

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

14. Core Cooling System ., ,'

1. HPSI and LPSI delivery curves See Tables 12 & Ref. 3, Attach. 1, gpm 13 Tables 3 & 4 Ref. 4, Attach. #3

2. SIT total volume. ft 2020 Ref. 4, Item 1.2.10

3. SIT initial pressure and liquid volume 215 Ref 4, Item 1.2.8 Minimum TS SIT pressure psia / (1090 to 1170) Ref. 4, Item 1.2.4 Nominal liquid volume in

/___

(190_to_1170) Ref._4,_Item_1.2. Mode 1.

4. CST minimum capacity gal 110,000 Ref 3, Attach. 1,

_________________________________________ ________________________Ite 8 _______Item____84_

5. Charging pump flow versus pressure Reciprocal pump. Flow is per charging pump.

40 (nominal) to 49 Ref. 3, Attach. 1, gpnil Nominal value does not (maximum) Item 15 include 4 gpm for RCP 15.a Control Systems Rated power operation of the primary and

L-2008-266 Attachment 1 Page 14 of 42 Item Parameter -Description Units Value Reference Comments No.

secondary control systems for:

1. SG water level instrumentation and control (he-emn)Later Later Later Later

. (three-element)

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

3. Pressurizer heaters and sprays Later Later Later Later

14. Pressurizer level Later Later Later Later

15. Auxiliary feedwater Later Later Later Later

6. CVCS (charging and letdown) --- Later Later Later Later 15.b Control System s *[.. .. .... ... * .... .. ..... ]

EPU condition operation of the primary and

• secondary control systems for: *

7. SG water level instrumentation and controlLaeL trL trLtr

, (three-element)

8. SG pressure (including bypass and ADV) Later Later Later Later i9. Pressurizer heaters and sprays Later Later Later Later i10. Pressurizer level Later Later Later Later S11. Auxiliary feedwater Later Later Later Later i12 9 'V ( "Q,(1-h nr oin oand letotr wn) I 1ntpr Tl t e," Tlntpr I n~tpor tn In

16. Reactor Vessel Upper Head Assume to be the same as core outlet temperature

1. Upper head fluid temperature at normal See item 1.b.3.4 OF Later since the Rx vessel does operating conditions. above.

not have upper head

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

L-2008-266 Attachment 1 Page 15 of 42 Item Parameter -Description Units Value Reference Comments No.

the valves for: ,

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. M SIVs ---- See Table 2----------

18 to 20 Reactor Core Parameters 1.Cnrlrdisrinvru ieatrseconds 3.1 Ref. 3, Itemn B7.18 Time for 90% insertion scram.

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

3. Reactivity versus fuel temperature and 'F vs Ap See Tables 7 & 8 Ref. 3, Items B13 reactivity versus moderator density. and B 14

4. Moderator temperature coefficient. 'F vs Ap See Table 9 Ref 3, Item B12

5. Typical top peaked axial power profile. Axial height (ft) vs. Axial See Table 10 Ref. 3, Item B16 Power Shape

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

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

8. Gap conductance. Later Later Later Later

9. Linear heat rate. kW / ft 15.0 (Max) 3, Ref. andItems B7.10 6.96 assumes 100 Value of Without 6.96 (Ave) II SS rods. this

L-2008-266 Attachment I Pa~e 16of 42 Item Parameter -Description Units Value Reference Comments No.

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 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 Ref. 1,, Setion Pumps Ref Section LOCA, and pumps loaded onto EDGs orare not None automatically trip 15.4.1. manal opte Same 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 equal to minimum subcooling None See Comment Ref. 18

• 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 between 60 and 70% NR,

• Rx Vessel level indicates

L-2008-266 Attachment I D* 11 fA)

Item PUs t Item Parameter -Description Units Value Reference Comments No.

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 Ref, 1, Section 10 minutes after a MSLB 15.4.6 and Ref 22 event. Same assumption for EPU analysis.

Most recent COLR provided to NRC via FPL ee See Comment See Comment letter L-2008-244, dated

22. Core Operating Limits Report SCm ne omt 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 Later Later Later Later

2. Specific heat Later Later Later Later

3. Thermal conductivity Later Later Later Later

4. Emissivity versus temperature Later Later Later Later

L-2008-266 Attachment 1 Page 18 of 42 Figure 1 PRESSURIZER LEVEL PROGRAM 100.0 80.0 (I

a.

Co

~0.

EU I- 60.0 0

-J w

w

-4 w

N 40.0 Co Co w

a.

20.0 0.0 506 522 . R538 554 570 586 602 VESSEL AVERAGE TEMPERATURE , TAVE (F)

Figure 2 - RCP Coastdown on Total Loss of Flow

1,POWER LEL Z.. MEPT FLUX

3. TOTAL. PRIMPRY COOLPN7 FLOW 12 1.001 a-.

>-00 11 Z-0 3.0 4.0 5.0 .0 7.0 801.

TIME, SEC Luie Uit Power, Heat. Flux and Flow -Loss O oln o St Figue 152,51 -

> K K)

L-2008-266 Attachment I Page 20 of 42

1, I Un!t I Figure 4 - Location of Fuel Assemblies in the Core

L-2008-266 Attachment 1 Page 21 of 42

,16i '*i*i.i i::lii!

331MM4__

Florida Poi St. Li Core oaao

-;,r '

L-2008-266 Attachment 1 Page 22 of 42 Table 1 Volume vs. Height for the Reactor Vessel with Internals Installed.

Region Elevation Volume vs. Height Volume (f) ( ft3 perf) ( ft3 )

UGS support plate to top of vessel 6.6 699 (Region V 6 )

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

Core Region (Fuel Alignment Plate (FAP) to CSP) (Regions V 2, V 3 & 12.8 69.7 892 V4)

CSB to vessel annulus (Region V 1, 29.7 35 1039.5 Annulus)

Bottom of vessel to Core Support Plate (CSP) (Region V 1, Lower 10 950.5 Plenum)

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

L-2008-266 Attachment 1 Page 23 of 42 Table 2 Component Data Required Component Flow Diagram Component Information Pressurizer PORVs V 1402 8770-G-078 Sheet 1 A, Rev 30 8770-9676 Rev 1 V 1404 8770-9677 Rev 2 8770-9678 Rev I 8770-9679 Rev 2 8770-9680 Rev 4 8770-9681 Rev 7 8770-9682 Rev 2 8770-9683 Rev 1 Pressurizer Safety Valves V 1200 8770-G-078 Sheet I 1A, Rev 30 8770-13730, Rev I 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)

FCV-08-644 8770-G-079, Sheet 2, Rev. 45 8770-103, Rev 7 FCV-08-645 8770-115, Rev 11 FCV-08-646 8770-116, Rev 24

L-2008-266 Attachment 1 Page 24 of 42 Component Flow Diagram Component Information 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 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 I 8770-G-079, Sheet 1, Rev. 53 8770-9673, Rev 10 HCV-08-lB Main Steam Check Valves V08117 8770-G-079, Sheet 1, Rev. 53 8770-8950, Rev 4 V08148 8770-895 1, Rev 2 8770-8952, Rev 0 8770-9673, Rev 10 8770-9674, Rev 8 Miscellaneous Components V2526 8770-G-078 Sheet 121A Rev. 38 V2501 8770-1380, Rev. 7 V2118 8770-1589, Rev. 9 V2623 8770-2699, Rev 2 V2500, 8770-853, Rev 1 V2101 8770-1589, Rev 9 V2322 8770-G-078 Sheet 120B Rev 17 8770-1592 Rev. 10 SS (Suction 8770-9301 Rev. 1 Stabilizer for 8770-9302 Rev. 5 Charging Pump IC)

SS-02-IC CHG PP IC 8770-205 Rev. 0 (Charging 8770-364 Rev. 4 Pump I C) 8770-12137 Rev. 5 8770-12138 Rev. 0 PD (Pulsation 8770-9982 Rev. 1 Damper on 8770-9981 Rev. 1 CHG PP IC)

V02134 8770-14099 Rev. 1 8770-14084 Rev. 1

L-2008-266 Attachment I Page 25 of 42 Component I Flow Diagram Component Information V2336 8770-14345 Rev. 1 8770-9379 Rev. 1 FE-2212 8770-23 10 Rev. 0 V2429 8770-1588 Rev. 5 V2430 8770-1571 Rev. 8 MV-02-2 8770-10468 Rev. 0 Regen HT 8770-420 Rev. 2 EXCH (Regenerative Heat Exchanger)

V2319 8770-1592 Rev. 10 SS-02-IB SS (Suction 8770-9301 Rev. 1 Stabilizer for Charging Pump IB) 8770-9302 Rev. 5 CHG PP 1B 8770-12137 Rev. 5 (Charging 8770-205 Rev. 0 Pump 1B) 8770-364 Rev. 4 8770-12138 Rev. 0 PD (Pulsation 8770-9982 Rev. 1 Damper on 8770-9981 Rev. 1 CHG PP 1B)

V02133 8770-14084 Rev. 1 8770-14099 Rev. 1 V2337 8770-14345 Rev. 1 8770-9379 Rev. 1 V2316 8770-1592 Rev. 10 SS-02-1A SS (Suction 8770-9301 Rev. 1 Stabilizer for 8770-9302 Rev. 5 Charging Pump IA)

CHG PP IA 8770-12137 Rev. 5 (Charging 8770-364 Rev. 4 Pump IA) 8770-12138 Rev. 0 8770-205 Rev. 0 PD (Pulsation Damper on CHG PP IA)

V2339 8770-14345 Rev. 1 8770-9378 Rev. 0 V02 132 8770-10883 Rev. 2 V2338 8770-1588 Rev. 5 SE-02-2 8770-12507 Rev. 0 8770-12508 Rev. 0 2998-19678 Rev. 0 2998-19677 Rev. 0 V2433 8770-14084 Rev. I

L-2008-266 Attachment I Page 26 of 42 Component Flow Diagram Component Information 8770-14099 Rev. 1 SE-02-1 8770-12507 Rev. 0 8770-12508 Rev. 0 2998-19677 Rev. 0 V2432 8770-1570 Rev. 10 V2519 8770-926 Rev. 13 8770-858 Rev. 2 V2515 8770-928 Rev. 8 8770-860 Rev. 4 V2516 8770-928 Rev. 8 8770-860 Rev. 4 V2341 8770-G-078 Sheet 120A Rev. 023 8770-1588 Rev. 5 LCV-2110P 8770-16166 Rev. 0 8770-787 Rev. 4 V2342 8770-1588 Rev. 5 LTDN 8770-419 Rev. 2 (Letdown Heat Exchanger)

V2347 8770-1578 Rev. 4 PCV-2201Q 8770-971 Rev. 9 V2349 8770-1591 Rev. 5 FE-2202 8770-2301 Rev. 1 V2358 8770-1592 Rev. 10 Purif FLTR 8770-14147 Rev. 1 lA 8770-558 Rev. 3 (Purification 8770-8852 Rev. 2 Filter IA) 8770-8617 Rev. 3 V2360 8770-1592 Rev. 10 V2520 8770-853 Rev. 1 V2369 8770-1592 Rev. 10 V2370 8770-1589 Rev. 9 V2378 8770-1592 Rev. 10 V2382 8770-1592 Rev. 10 V2395 8770-1592 Rev. 10 S2900 8770-1480 Rev. 1 V2415 8770-1592 Rev. 10 V2418 8770-1592 Rev. 10 Purif FLTR 8770-14147 Rev. 1 1B 8770-558 Rev. 3 (Purification 8770-8852 Rev. 2 Filter 1B) 8770-8617 Rev. 3 V2452 8770-1592 Rev. 10 FE-8011 8770-G-079, Sheet 1, Rev. 53 8770-965, Rev 5 FE-8021 8770-965, Rev 5 V09252 8770-G-080, Sheet 3, Rev 54 8770-5736, Rev 4 V09294 8770-7139, Rev 3 AFW PP lA 8770-G-080, Sheet 4, Rev. 41 8770-3044, Rev 3 AFW PP lB 8770-4409, Rev 0

L-2008-266 Attachment 1 Page 27 of 42 Component Flow Diagram Component Information 8770-15879, Rev 0 AFW PP IC 8770-3183, Rev 7 8770-4408, Rev 0 V09139 8770-1398, Rev 6 V09140 8770-1257, Rev 3 FE-09-2C 8770-3544, Rev 0 8770-3294, Rev 4 MV-09-11 8770-6967, Rev 5 MV-09-12 8770-6967, Rev 5 V09151 8770-3775, Rev 6 V09157 8770-3775, Rev 6 V09152 8770-3774, Rev 3 V09158 8770-1251, Rev 2 V09123 2998-20110, Rev 1 V09107 8770-3775, Rev 6 V09108 8770-1251, Rev 2 V09124 8770-1251, Rev 2 FE-09-2A 8770-3294, Rev 4 FE-09-2B 8770-3544, Rev 0 MV-09-9 8770-6966, Rev 5 MV-09-10 8770-6966, Rev 5 V09119 8770-3775, Rev 6 V09135 8770-3775, Rev 6 V09120 8770-3774, Rev 3 V09136 8770-1251, Rev 2 V1403 8770-G-078 Sheet lOA, Rev 30 8770-1374, Rev 10 V1405 8770-1374, Rev 10 V1406 8770-1750, Rev 5 V 1407 8770-1750, Rev 5 PZR Quench 8770-898, Rev 3 Tank V1252 8770-1769, Rev 4 V1253 8770-1769, Rev 4 PCV- I1OOE 8770-864, Rev 2 PCV- I1OOF 8770-970, Rev 15 V1248 8770-6586, Rev 3 V 1249 8770-6777, Rev 1 8770-16184, Rev 0 V1250 8770-1769, Rev 4 8770-16184, Rev 0 V1251 8770-1769, Rev 4 SO-03-13 8770-G-078 Sheet 130A, Rev 27 SO-03-14 SO-03-15 V3427 8770-1768, Rev 8 V3405 8770-1768, Rev 8 V3414 8770-1768, Rev 8 V3654 8770-1377, Rev 6

L-2008-266 Attachment I Page 28 of 42 Component I Flow Diagram Component Information V3656 8770-1377, Rev 6 HCV-3616 8770-G-078 Sheet 131A, Rev 27 8770-1376, Rev 5 HCV-3626 8770-1376, Rev 5 HCV-3636 8770-1376, Rev 5 HCV-3646 8770-1376, Rev 5 V3113 8770-12709, Rev 10 V3123 8770-1570, Rev 10 V3133 8770-1570, Rev 10 V3143 8770-1570, Rev 10 FE-3311 FE-3321 FE-3331 FE-3341 HCV-3615 8770-1375, Rev 6 HCV-3625 8770-1375, Rev 6 HCV-3635 8770-1375, Rev 6 HCV-3645 8770-1375, Rev 6 V3114 8770-1748, Rev 7 V3124 8770-1748, Rev 7 V3134 8770-1748, Rev 7 V3144 8770-1748, Rev 7 FE-3312 8770-2301, Rev 1 FE-3322 8770-2301, Rev 1 FE-3332 8770-2301, Rev 1 FE-3342 8770-2301, Rev 1 HCV-3617 8770-1376, Rev 5 HCV-3627 8770-1376, Rev 5 HCV-3637 8770-1376, Rev 5 HCV-3647 8770-1376, Rev 5 V3106 8770-G-078 Sheet 130B, Rev 31 8770-3646, Rev 1 V3107 8770-3646, Rev 1 V3206 8770-9348, Rev 3 V3207 8770-9348, Rev 3 FCV-3306 8770-86 1, Rev 2 8770-930, Rev 8 FE-3306 8770-2301, Rev 1

L-2008-266 Attachment 1 Page 29 of 42 Table 3

L-2008-266 Attachment 1 Page 30 of 42 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.

N

L-2008-266 Attachment I Page 31 of 42 Table 5 - Single Phase Homologous Head and Torque Curves CURVE 1 CURVE2 CURVE3 CURVE4 CURVE5 CURVE6 CURVE7 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-2008-266 Attachment 1 Page 32 of 42 Table 6 Unit 1 Piping Isometric Drawings by P&ID Flow Diagram F Isometric/Component Drawing Reactor Vessel 8770-G-078, Sheet IIOB, 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 1 OB, Rev. 26 8770-39, Rev 3 8770-40, Rev 3 8770-530, Rev 3 8770-781, Rev 3 8770-880, Rev 1 8770-1496, Rev 2 Reactor Coolant Pumps 8770-G-078, Sheet II1A, Rev. 15 8770-15, Rev 8 8770-G-078, Sheet 11 1B, Rev. 15 8770-178, Rev 11 8770-G-078, Sheet 11 IC, Rev. 14 8770-54, Rev 9 8770-G-078, Sheet 11ID, Rev. 16 Steam Generators 8770-G-078, Sheet 1 OB, 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 110A, 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-I187, Rev I

L-2008-266 Attachment I Page 33 of 42 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 13 1A, 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 110B, Rev. 26 8770-G-125 Sheet CH-G-1 Rev. 2 8770-G-078, Sheet 120A, Rev. 23 8770-G-125 Sheet CH-G-2 Rev 1 8770-G-078, Sheet 120B, Rev. 17 8770-G-125 Sheet CH-G-3 Rev 4 8770-G-078, Sheet 121A, Rev. 38 8770-G-125 Sheet CH-G-4 Rev 0 8770-G-078, Sheet 121B, Rev. 32 8770-G-125 Sheet CH-G-5 Rev 0 8770-G-088, Sheet 1, Rev. 51 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 8770-B-124 Sheet CH-43 Rev 5 8770-B-124 Sheet CH-63 Rev 7

L-2008-266 Attachment 1 Page 34 of 42 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-2008-266 Attachment 1 Page 35 of 42 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 808.1 946.5 -0.0128639

-0.0186432 No changes from current No changes from current 107.9 -0.0181490 analysis 1077.9 -0.0181490 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(Ibm/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.oxi01 Note: Reactivity corresponding to the most positive MTC @ HFP, BOC

L-2008-266 Attachment 1 Page 36 of 42 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 003959 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 (n ... (*) (n)_____......_____

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-2008-266 Attachment I Page 37 of 42 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 > 11IF but < 200 0 F.

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) +/- 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 I°F but < 200'F.

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 > I11 OF but < 200 0 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+/- 3% (tolerance)

PZR Safety RV N/A 2500 psia (nominal) + 3%, - 2.5% (tolerance) + 3%, - 2.5% (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-2008-266 Attachment 1 Page 38 of 42 TABLE 12 ST. LUCIE UNIT 1 - HIGH PRESSURE SAFETY INJECTION PUMP DELIVERY FLOWIPUMP DEGRADED PUMP NON-DEGRADED PUMP NOMINAL MINIMUM NOMINAL MAXIMUM 4-LOOP 3-LOOP 4-LOOP 3-LOGP RCS 4-LOOP LOWEST TOTA MINIMU RCS 4-LOOP HIGHEST TOTA MAXIMU PRESSLRE TOTAL 3-LOOPS MON ANIS PRESSURE TOTAL 3-LOOPS TAL ANALSI MIN ANALYSIS MAX ANALYSIS (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-2008-266 Attachment 1 Page 39 of 42 Table 13. ST. LUCIE UNIT 1 - LOW PRESSURE SAFETY INJECTION PUMP DELIVERED FLOW Min Degraded LPSI Min Degraded LPSI Flow/Pump (4 Valves) I Max LPSI Flow/Pump (4 Valves)

Max LPSI Flow with Two Pumps (4 Valves) I I

Flow/Pump (2 Valves) I RCS TOTAL 3-LOOP RCS TOTAL 3-LOOP RCS TOTAL 3-LOOP RCS TOTAL 1-LOOP PRESSURE FLOW MINIMUM PRESSURE FLOW MAXIMUM PRESSURE FLOW MAXIMUM PRESSURE FLOW MINIMUM (PSIA) (GPM) (GPM) (PSIA) (GPM) (GPM) (PSIA) (GPM) (GPM) (PSIA) (GPM) (GPM) 144.44 0 0 202.48 0 0 202.48 0 0 144.44 0 0 144.42 61 45 202.46 56 43 202.41 111 85 144.37 61 30 144.29 161 119 202.34 156 119 201.96 311 238 143.98 161 79 143.22 461 340 201.30 456 348 198.03 911 697 140.64 461 225 141.54 711 525 199.65 706 540 191.81 1411 1079 135.41 711 347 138.92 961 709 197.01 956 731 182.62 1911 1462 127.72 961 469 134.83 1211 894 192.68 1206 922 169.77 2412 1844 117.05 1211 591 129.61 1461 1078 187.10 1456 1114 153.70 2912 2227 103.73 1461 713 123.24 1712 1263 180.25 1706 1305 134.38 3413 2610 87.73 1712 835 115.69 1962 1447 172.10 1957 1497 111.78 3913 2993 69.04 1962 957 106.95 2212 1632 162.61 2207 1688 85.86 4414 3376 52.14 2162 1055 96.99 2463 1817 151.76 2458 1880 56.60 4915 3759 47.64 2212 1080 85.78 2713 2002 139.52 2708 2071 23.96 5416 4143 43.02 2262 1104 73.31 2964 21.87 125.86 2959 2263 17.02 5517 4219 33.47 2363 1153 44.47 3466 2557 94.14 3461 2647 23.48 2463 1202 10.30 3968 2927 56.39 3963 3031 18.32 2513 1226 Each LPSI 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-2008-266 Attachment I Page 40 of 42 Table 14 Primary Loop Pressure Drop Distribution Geometry AP Geometry AP Friction Forward Reverse Flow Reference #

Station AP Flow EPt Values> (tpsi (PsXfi) (I *I 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

/ PressureA ~

~Current Values~ dr-o (si)' ~,

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.

L-2008-266 Attachment 1 Page 41 of 42 Appendix A - Calculation of Fuel Assembly Grid Weight and Surface Area 9 U.V1 S 0.01 side s HTP HMP Grd Mý REFERENCES

L-2008-266 Attachment I Page 42 of 42

1. St. Lucie Unit 1 UFSAR, Amendment 22.

2. St. Lucie Unit 1 Technical Specifications, Amendment 204.

3. FPL Letter NF-08-223, Revision I to St. Lucie Unit 1 Extended Power Uprate Input Data (EPU AID-i), dated June 30, 2008..

4. FPL Letter NF-08-229, Revision 1 to St. Lucie Unit 1 EPU Safety Analysis Parameters (EPU SAPP-1), dated July 02, 2008.

5. PSL-ENG-SEMS-08-040, Revision 1, Extended Power Uprate -HTPSI Fathom Model Input Data Request St Lucie Nuclear Plant Unit 1.

6. PSL-ENG-SEMS-08-029, Revision 4, Extended Power Uprate -Input Data Request St Lucie Nuclear Plant Unit 1.

7. St. Lucie Procedure 1-012005 1, Revision 22B.

8. St. Lucie Unit 1 Safety Analysis Plant Parameters (SAPP-1), Revision 10.

9. Shaw Stone & Webster Drawing 12915401-HB(S)-101-2 dated 2/28/08.

10. Shaw Stone & Webster Drawing 12915401-HB(S)-109-2 dated 2/28/08.

11. B&W Report BWI-222-7698-PR-01, "Replacement Steam Generators Performance Data Report," Revision 1.

12. AREVA NP Document EMF-2475(P), Revision 1.

13. St. LucieDrawing 8770-8863, Fuel Assembly Alignment Plate (As-Built), Sheet 1, Rev. 0.

14. St. Lucie Drawing 8770-8864, Fuel Assembly Alignment Plate(As-Built), Sheet 2, Revision 0.

15. St. Lucie Vendor Manual, VTM 8770-6945, Reactor Vessel Internals, Revision 3.

16. St. Lucie Drawing 8770-15, Outline Primary Coolant Pump Vertical, Revision 8.

17. St. Lucie Annunciator Procedure 1-ARP-01-J00, Control Room Panel J, Rev. 4A.

18. St. Lucie Emergency Procedure 1-EOP-03, Loss of Coolant Accident, Rev. 26.

19. B&W Report, BWI-222-7698-PR-01, "RSG Data Report"

20. AREVA Drawing 5041824, Cage Assembly, Revision 1 (Proprietary)

21. St. Lucie Drawing 8770-13348, General Arrangement (Steam Generators), Rev. 1.

22. FPL Letter NF-08-262, dated 8-8-08

23. B&W Report CM9021278-PR-01 Revision 0.

24. FPL Drawing 8770-13266, Tube Length & Quantity (Ordering), Revision 0

25. Deleted.

26. St. Lucie Evaluation PSL-ENG-SEFJ-06-016, Evaluation of Proposed St. Lucie Unit 1 Cycle 21 Fuel Design/Manufacturing Changes, Revision 0.

27. B&W Calculation CM9021278-A03, Rev. 0, December 1, 2008.

28. Westinghouse Letter PCWG-08-33, Rev. 1, "Approval of Revised Category HIP (for Limited Scope Contract) PCWG Parameters for Unit 1 and Revised Category III (for Contract) PCWG Parameters for Unit 2 to Support the EPU Program", dated 11-4-08.

29. Engineering Evaluation PSL-ENG-SEMS-97-054, Rev. 0, "Review of Plant Operation with Replacement Steam Generators", October 30, 1997.

30. Westinghouse Letter FPL-08-117, "Extended Power Uprate: NRC Data Request", December 16, 2008.

L-2008-266 Attachment 2 Page 1 of 46 ST. LUCIE UNIT 2 EPU Input Data Request to NRC for LOCA Model Item Parameter -Description Units Value Reference Comments No.

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

l.Primary and Secondary Flow rates: * * , **** , , ': *"***,,,,

1. 1. C ore flow Ref ,3, A ttach. 2. n :+1 ,0 gp a d mi gpm 412,000 Ref, 6, Items 9 and 8 for fo s3 50 0 uncertainty and min flow.

1.2. Main coolant pumps 97,500 (2A1) 96,000 (2A2) Ref. 6, Table 2 RCP Pump Test Data 95,000 (2B1) 94,000 (2132) 1.3. Steam flow ibm/hr See Item la SeItml 7.1 1.4. Feedwater flow lbm/hr See Item la SeItml 7.1 1.5. SG recirculation ratio/boiler section flow Power %Circ Ratio Power- 20 18.41 50 7.91 Ref8

%CircRatio 70 5.42 90 3.96 100 3.46

2. Primaly and Secondary Pressures:

2.1. Pressurizer Nominal Operating Pressure is 2250 psia. Pressure range is psia 2250 Ref. 6, Item 4 2225 to 2275, with Unc: +/- 45 Normal, + 90 Accident.

L-2008-266 Attachment 2 Page 2 of 46 Item Parameter -Description Units Value Reference Comments No. I 2.2. Core inlet Based on 2250 psia core outlet psia 2286 and 35.5 psi core pressure drop (UFSAR Table 4.4-4).

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

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

2.5. Steam generator dome SG outlet pressure from 886.81 Refs. 8 and 15 benchmnark heat balance plus dP to upstream of flow restrictor 2.6. Turbine control valve inlet See Item la psia 7.3 2.7 Detailed primary loop pressure drop Table 13 Assumes 10% SG tube distribution below Ref 21 plugging.

3. Primary and Secondary Temperatures:

3. 1. Hot leg Assumed to be the same as the OF60 ------- core outlet temperature since

°F600the Rx vessel does not have upper head injection.

3.2. Cold leg OF 549 Ref. 6, Item 6. Tcold temperature at full Unc: +/--3OF power.

3.3. Core outlet Based on Tcold of 549F and F 600 Ref 3, Attach 3574F.

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

4. Water levels in the pressurizer and steam generators,

L-2008-266 Attachment 2 Page 3 of 46 Item Parameter -Description Units Value Reference Comments No.

4.1. Pressurizer Ref 6, Attachment #1,

% Tap Span See Figure 1 Figure 3.

4.2. Steam Generators in 411.3 Ref. 8 Level above tubesheet

5. Leakage flows (Bypass):  % of vessel Ref 6, Item 10. This is the total core bypass 3.7 Ref. 1, Table 4.4-3 for maximum value for minimum bypass breakdown. core flow rate.

5.1. Outlet nozzle clearances Ref. 7 Table 443 and Ref Assume bypass breakdown percent 1.12 1, Figure 4.4-6 documented in Unit I UFSAR due to unit similarities.

5.2. Downcomer to upper head Ref. 7, Table 4.4-3 and Rf Assume bypass breakdown percent 0.16 1, Figure 4.4- . documented in Unit 1 UFSAR u4.4-6 due to unit similarities.

5.3. CEA shrouds Equivalent to a fraction of the leakage through guide tubes percent N/A (item 1a.5.5.1). This has not been quantified.

5 .4 . U p p e r h e a d to up p e r p le n u m (g u id e p r e tN A- --- h sh s n t b e u nii d structure holes)pecnN/Thshsntbnqutied 5.5. Core bypass (guide tubes, barrel-baffle) 5.5. 1. Guide tubes Ref. 7, Table 4.4-3 and Assume bypass breakdown percent 1.76 documented in Unit 1 UFSAR Ref. 1, Figure 4.4-6 due to unit similarities.

5.5.2. Barrel-baffle Ref 7, Table 443 and Rf Assume bypass breakdown percent 0.47 F able 4.4-6 e, documented in Unit 1 UFSAR 1, Figure 4.4-6 due to unit similarities.

6. Steam generator recirculation ratio Power- See Item I a

%CircRatio 1.5

7. Heat balance information such as:

L-2008-266 Attachment 2 Page 4 of 46 Item Parameter -Description Units Value Reference Comments No.

7.1. Feed and steam flows 11,905,010 Ibm/hr 1 Ref. 15 Benchmark Heat Balance 11,806,740 7.2. Feedwater temperature OF 435

°F 45 Ref Re. 1515Benchmark Heat Balance 7.3. Turbine inlet pressure. psa827 Rf 5Benchunark Heat Balance, Turbine Inlet Valve

1. Plant Operating Conditions lb. 'For EPU conditions.

1. Primary and Secondary Flow rates: i L.1. C ore flow Ref ,3, Attach. 2. e o i i u l wi 7 ,0

• ~ ~~gpm 412,000 Ref, 3, Attach. 1, Ite 8 o Mnmumfo s 7,0 rain flow. gm 1.2. Reactor coolant pumps 97,500 (2A1) gpm 96,000 (2A2) Ref 3, Attach #1, Table 2. RCP Pump Test Data gpm 95,000 (2B 1) 94,000 (2B2) 1.3. Steam flow lbm/s See Item lb 7.1 1.4. Feedwater flow lbm/hr See Item lb 7.1 1.5. SG recirculation ratio/boiler section Power %Circ flow Power- Ratio 25 13.86

%CircRatio 50 75 7.

4.40 n93 em 17 100 3.02

2. Primary and Secondary Pressures (absolute * ,* , i*** ,**,,

pressures): * * *,** .. ,,,*****'*

2. 1. Pressurizer /[Ref. 3, Attach#41, Item 4. Range: 2225 to 2275 psia.

psia 2250 Ref. 3, Item D. 17 for Unc.: +_45 psi normal, unetit.+ 90 psi harsh.unetiay

L-2008-266 Attachment 2 Page 5 of 46 Item Parameter -Description Units Value Reference Comments No.

2.2. Core inlet psia 2286 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 2287 Assumed to remain similar to current conditions.

2.5. Steam generator dome psia Later Later Later 2.6. Turbine control valve inlet psia See Item Slb.7.3 2.7 Detailed primary loop pressure drop Table 13 Ref, 21 Assumes 10% SG tube distribution psi below plugging.

3. Primary and Secondary Temperatures: M,,*itI 3.1 Hot leg OF 606.0 Ref. 19 Assumes 10% SG tube plugging.

3.2 Cold leg 551 Ref. 3, Attach. 1, Items 6. Corresponds to 100% Power.

OF UncC +/-3F Ref. 3, Attach. 1, Item 7 for Tcold at zero power is 532F.

codtzopeiF3Tcold.

3.3 Core outlet OF 607.9 Ref. 19 Assumes 10% SG tube plugging.

3.4 Upper Head OF 606.0 Ref. 19 Assumed to be the same as

• outlet.*

• vessell~l*

• 4 Water levels in the pressurizer and steam generators **,,,,*,*

4.1 Pressurizer  % Tap Span See Figure 1 Ref. 3, Attachment #1, below Figure 3.

4.2 Steam Generators in 411.3 Ref 8 Level above tubesheet 5 Leakage flows:  % of vessel 3.7 Ref 3, Iten D.

flow 5.1 Outlet nozzle clearances percent 1.12 Ref, 7, Table 4.4-3 and Ref, Assumed to be similar to 1, Figure 4.4-6 current operating value.

5.2 DC to upper head percent 0.16 Ref. 7, Table 4.4-3 and Ref, Assumed to be similar to 1, Figure 4.4-6 current operating value.

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

L-2008-266 Attachment 2 Page 6 of 46 Item Parameter -Description Units Value Reference Comments No.

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

structure holes) 5.5 Core bypass (guide tubes, barrel-baffle) ,

5.5.1 Guide tubes percent 1.76 Ref. 7, Table 4.4-3 and Assumed to be similar to Ref.1, Figure 4.4-6 current operating value.

5.5.2 Barrel-baffle percent 0.47 Ref 7, Table 4.4-3 and Ref Assumed to be similar to 1, Figure 4.4-6 current operating value.

6 Steam generator recirculation ratio Power- See Item

_________________________________ %CircRatio lb. 1.5

%-Ci 1b...5 7 Heat balance information such as:

lbm/hr Later Later Will be provided when 7.1 Feedwater and steam flows finalized 7.2 Feedwater temperature OF Later Later WillI be provided when finalized 7.3 urbne iletpresurepsi Laer LterWill be provided when 7.3 urbne iletpresurepsi Laer Lterfinalized

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

CENPD- 132, through Suppl. 4-P-A, "Calculative Method for

1. Topical Report on the licensing analysis Seethe CE Nuclear Power of record for LOCA at rated power and Comment Comment See Comment Large Break LOCA EPU conditions. Evaluation Model",

March 2001.

• CENPD-137, through Suppl. 2-P-A, "Calculative Method for the ABB CE Small Break LOCA Evaluation

L-2008-266 Attachment 2 Page 7 of 46 Item Parameter -Description Units Value Reference Comments No.

Model", "April 1998.

No new Topical Reports for EPU analyses. Analysis results are in the UFSAR.

Safety System Logic, Setpoints and Delay

3. Times,. ,

Critical Safety Parameters List (also called *t , ,,, " ,' '... ,  :

"Groundrules document") for the last reload I**

fo r: f

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

2. RPS See Table 5 See Table 5 See Table 5 See Table 5

3. SGIS/MSIS See Table 5 See Table 5 See Table 5 See Table 5

4. PORV See Table 5 See Table 5 See Table 5 See Table 5

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

4. Primary and Secondary Pressure Drops

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

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

5. Core and Fuel Design I. Number of assemblies "N/A 217 Ref. 1, Table 4.2-10 ----

2. Dimensions Array: 16 x Ref 1, Table 4.2-10, and N/A 16, Pitch: re.The pitch is the sum of 7.972 8.180 in, Figures 4.1-2, 4.2-6. and 0.208 = 8.180 in.

Length: Also, Ref. 13.

L-2008-266 Attachment 2 Page 8 of 46 Item Parameter -Description Units Value Reference Comments NO.

158.5 in

3. Spacer grid locations and K-factors See Table 4 Refs. 14 (Proprietary) and N/A for grid 18 show grid locations and Spacer grid K-factors to be locations, dimensions, provided later.

4. Vessel pressure drops Current values:

a) Inlet nozzle & 90 degree a) 5.0 turn, psi b) 10.4 Ref. 1, Table 4.4-4 b) Downcomer, lower plenum, c) 13.4 support structure, d) 6.7 c) Fuel assembly, d) Fuel assembly outlet to outlet nozzle.

5. Bypass and leakage flows  % of totalflw a5.See item boe See item 1a.5.5 above Similar to Item 1a.5.5 above.

flow la.5.5 above

6. Number and location of fuel rods. 236 per assy 51,212 total. Ref. 1, Section 4.1 and Some fuel rods contain N/A See Figs. 3 Figs. 4.1-2 and 4.3-65 for burnable absorber material.

and 4 below locations.

for location.

7. Number and location of guide tubes. 5 guide tubes per assy.

See Fig. 3 Ref, 1, Section 4.1, and Fig.

N/A below for 4.1-2 for location.

location.

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 equipment:

L-2008-266 Attachment 2 Page 9 of 46 Item Parameter -Description Units Value Reference Comments No.

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, cold leg, pump See Table 3 .......

suction)

3. Reactor coolant pumps --- See Table 3

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

5. Pressurizer, surge line, spray lines, safety See Table 3 and relief valves 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 --- See Table 3 valves to the steam generator inlet.

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

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

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

1. . Residual heat removal system. See Item 6.9 for LPSI System.

See LPSI and RHR are the same Comments -C'ijtp

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

L-2008-266 Attachment 2 Page 10 of 46 Item Parameter -Description Units Value Reference Comments No.

8. Core support barrel Includes upper, center, and 136,600 / lower portions of the core Lbs / sq. ft. 1126 Inside Ref 20 support barrel; upper and 1110 outside lower flange; inner and outer nozzle areas.

9. Core shroud 34,000 / Includes vertical and Lbs / sq. ft. 594 Inside Ref. 20 horizontal surfaces of the core 867 outside shroud.

10. Lower core support plate Includes top and bottom Lbs / sq. ft. 8,000 / 260 Ref. 20 surfaces; surface areas inside the holes of the plate.

11. Fuel alignment plate (Upper Core Plate) Includes top and bottom Lbs / sq. ft. 9,900 / 331 Ref 20 surfaces; surface areas inside the holes of the plate.

12. Upper guide structure Includes CEA shrouds with extensions; total UGS plate, Lbs /sq. ft. 120,000 / Ref 20 flange, beam, & cylinder 7,120 areas; total fuel alignment plate area (Neglects guide tubes).

13. Core support assembly Includes vertical webs; Lbs /sq. ft. 45,500 / Ref. 20 flanges; cylinder; columns; 1193 core support plate; bottom plate.

14. Flow skirt Includes top and bottom Lbs / sq. ft. 3,600 / 223 Ref 20 surfaces; surface areas inside the holes of the plate.

15. Control element assembly (CEA) shrouds 48,000/ Does not include shroud Lbs / sq. ft. 1826 Inside Ref 20 Doesnonc s 2100 outside extensions.

16. Shroud extensions 10,400 /

Lbs / sq. ft. 866 Inside Ref. 20 1035 outside

17. Grid assemblies 18.5 / 5.0 Ref 20 Each assembly has 9 grids for Lbs/psq. ft. RGrid 217 assemblies.

L-2008-266 Attachment 2 Page 11 of 46 Item Parameter -Description Units Value Reference Comments No.

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 1.2. Surface area of Tube Sheet (Primary Side)

2. Weight and surface area of steam generator wrapper.

2.1. Weight of SG wrapper I Ibm 34,730 1 Ref. 8 I Includes wrapper roof 2.2. Surface area of SG wrapper ft2 Later Later Later

9. Steam Generator Fluid Volumes

1. Inlet plenum Wt 338.4 Ref. 8 Includes Manway

2. Outlet plenum Wt 332.0 Ref. 8 Includes Manway

3. Active and W 1230.0 Ref. 8 inactive (within tube sheet) tubes 41.3

4. Number of steam generator tubes 8999 Ref. 8

5. Length of shortest and longest ft Later Later Later

10. Steam Generator Parameters

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

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

L-2008-266 Attachment 2 Page 12 of 46 Item Parameter -Description Units Value Reference Comments No.

11. MS Line Flow Restrictor 3.791 to

1. Restrictor flow area ft2 3.803 per Re3,ScinE2ad24 OultNzeAr, SG, ef3,ScinE2an2.FlowO leVenturiN zlArea~ra 2.27 per SG

12. Steam Generator Heights and Reactor Vessel *l i *i i ......

1. Volume versus height relationship for the steam generators with downcomer and boiler See Table 6 See Table 6 Ref. 1, Table 4.4-8 ----

regions provided separately

2. V olum e versus height for the reactor vessel S e T b e6 S e T b e6 Rf ,T b e4 4 8- -- -

with internals installed

13. Reactor Coolant Pump Rated Conditions

1. Head The value is the average of the ft 296.75 Ref, 3, Item B.7. four pump-specific values (303, 296, 293 & 295 ft)

2. Flow The value is the average of the 87,750 Ref. 3, Item B.8. (8,0 -8,0900 gpm (85,000 - 87,500 - 91,000 &

87,500 gpm)

3. Torque The value is the average of the ID.6. four pump-specific values (33,860 - 34,000 - 34,720 &

33,230 ft-lbf)

4. Speed rpm 900 Ref. 3, Item D.4. Synchronous speed

5. Density Ibm/ft3 47.5 Ref, 3, Attach.I, Item 14 The value is the average of the

L-2008-266 Attachment 2 Page 13 of 46 Item Parameter -Description Units Value Reference Comments No.

four pump-specific values (47.3, 47.4, 46.9 and 48.4 Ibm/

f3)

6. Homologous pump curves (four quadrant) N/A See Table 7 Ref. 3, Table 2.

7. Pump inertia and friction (coefficients of Uncertainty value of+ 1%

polynomial in pump speed) lbm-ft2 102,000 Ref. 3, Attach. .1, Item 14 may be applied to pump inertia in the analysis to gain ft-lbf 2735 Ref 3, Item B.3. operating margin.

- Constant for friction and windage torque.

8. Coolant primary system fluid volume within W 112 Ref. 10 pump

9. RCP metal mass, excluding motor lbs 75,000 Ref. 10 Dry weight.

10. Reverse rotation device operational for RCP design torque for anti-RCPs N/A Yes Ref, 3, Item B 1. reverse rotation device equal to 62,000 ft-lbf

11. Pump power to primary fluid 14.2 MWt (nominal), Ref. 3, Attach. 1, Item 12 ----

20 (rnax)

12. Coastdown characteristics N'/A Figure 2 Ref. 1, Figure 15.3.2-1 -----

13. Pump trip setpoints N/A Overcurrent Ref. 12 Overload Trip

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

14. Core Cooling System

1. H-PSI and LPSI delivery curves See Tables 8, Ref, 3, Attach. 1, Tables 3, ----

gpm 9, 10,1l1 4, 5, 6

2. SIT total volume Wt 1855 Ref. 1, Table 6.3-1 Four tanks, each with this capacity.

3. SIT initial pressure and liquid volume (500 to

• psia 650 + 15)

• Ref 3, Item E. 10 TS ranges for SIT pressure ft3 W * (1420 to

• Ref 3, Item E.9 and liquid volume.

1556 + 32)

L-2008-266 Attachment 2 Page 14 of 46 Item Parameter -Description Units Value Reference Comments No.

4. CST minimum capacity gal 276,200 Ref. 3, Attach. 1, Item 84

5. Charging pump flow versus pressure 40 (nominal) to 49 Reciprocal pump. Flow is per (maximum) Ref. 3, D.27 charging pump. Nominal 35 minimum, m value does not include 4 gpm after for RCP bleed-off.

uncertainties 15.a Control Systems Rated power operation of the primary and* ***

secondary control systems for:

1. SG water level instrumentation and controlLaeLtrL trL tr

, C(three-element)

2. 3PrsuiehetranspasLater SG pressure (including bypass and ADV) Later Later Later LaterLae Later Later

3. Pressurizer heaters and sprays Later Later Later Later

4. Pressurizer level Later Later Later Later

5. Auxiliary feedwater Later Later Later Later

6. CVCS (charging and letdown) Later Later Later Later 15.b Control Systems l*

EPU condition secondary operation control systemsoffor:

the primary and * ***I* ' ,* ,,, * ,, , fi, ,,

7. SG water level instrumentatioln and controlLaeL trL trL tr (three-element)

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

9. Pressurizer heaters and sprays Later Later Later Later

10. Pressurizer level Later Later Later Later

11. Auxiliary feedwater Later Later Later Later

12. CVCS (charging and letdown) Later Later Later Later

L-2008-266 Attachment 2 Page 15 of 46 Item Parameter -Description Units Value Reference Comments No.

16. Reactor Vessel Upper Head Assume to De me same as ine

1. Upper head fluid temperature at normal core outlet temperature since OF Later See item l.b.3.4 above.

the Rx vessel does not have operating conditions.

unnnr hpnd inipftion

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:

1. Pressurizer PORVs See Table 12 1

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. M SIVs ---- See Table 12---------

18.

to Reactor Core Parameters 20.

I. Control rod insertion versus time after scram Later Later Later Later

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

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

L-2008-266 Attachment 2 Page 16 of 46 Item Parameter -Description Units Value Reference Comments No.

4. Moderator temperature coefficient Later Later Later Later

5. Typical top peaked axial power profile Later Later Later Later

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

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

8. Gap conductance Later Later Later Later

9. Linear heat rate Later Later Later Later

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

21. Operator Actions During LOCA

1. Reactor coolant pump trips (conditions to Accident analysis assumes trip pumps - automatic or manual). Pumps LOOP concurrent with LOCA, None automatically Ref. 1, Section 15.6.5. and pumps are not loaded into trip on EDGs or manually operated.

LOOP 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 See than or None Comments Ref. 11 equal to minimum subcooling Section. - Pressurizer level is at least 30%

and NOT lowering,

- At least ONE S/G is available for RCS heat removal with level

L-2008-266 Attachment 2 Page 17 of 46 Item Parameter -Description Units Value Reference Comments No.

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 feedwater control Due to the design of the AFW system that automatically isolates the AFW from the broken loop, no auxiliary N/A See comment Ref. I, Section 15.1.6 feedwater was assumed to be delivered during the post-trip MSLB event. No flow delivered for pre-trip MSLB either.

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

22. Core Operating Limits Report Comment Comment See Comment 183, dated 11-19-2007. 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, t.:. . ...

1. Density Later Later Later Later

2. Specific heat Later Later Later Later

L-2008-266 Attachment 2 Page 18 of 46 Item Parameter -Description Units Value Reference Comments No.

3. Thermal conductivity Later Later Later Later

4. Emissivity versus temperature Later Later Later Later

L-2008-266 Attachment 2 Page 19 of 46 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 +

0.

CL 50 t I--

.-J w

45 -

w

.-J w

40 T Cn 0-35 (538.2, 33.1) 30 4 25 4-520.0 530.0 540.0 550.0 560.0 570.0 580.0 590.0 TAVE (F)

Pressurizer Volume at 63.0% Span is 914 Cu. Ft.

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

L-2008-266 Attachment 2 Page 20 of 46 Figure 2 - RCP If I

kM1eomUIten".o, Note: Curve represents current analyses.

L-2008-266 Attachment 2 Page 21 of 46 Figure 3

L-2008-266 Attachment 2 Page 22 of 46 Figure 4

L-2008-266 Attachment 2 Page 23 of 46 Table 1 (Later)

L-2008-266 Attachment 2 Page 24 of 46 Table 2 (Later)

L-2008-266 Attachment 2 Page 25 of 46 Table 3 Unit 2 Piping Isometric Drawings by P&ID Flow Diagram Component/Isometric Drawing Reactor Vessel 2998-G-078, Sheet I110, 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 2998-1886, Rev. 6 Reactor Coolant Pumps 2998-G-078, Sheet 1I1A, Rev. 11 2998-455, Rev. 6 2998-G-078, Sheet 111B, Rev. 10 2998-457, Rev. 8 2998-G-078, Sheet I I IC, Rev. 13 2998-G-078, Sheet 11 ID, Rev. 10 Steam Generators 2998-G-078, Sheet 110, Rev. 8 l 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-L73, 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-125, Sheet SI-N-4, Rev. 20 2998-G-078, Sheet 130B, Rev. 28 2998-G-125, Sheet SI-N-5, Rev. 19 2998-G-078, Sheet 13 1, Rev. 20 2998-G-125, Sheet SI-N-6, Rev. 18 2998-G-078, Sheet 132, Rev. 09 2998-G-125, Sheet SI-N-7, Rev. 15 2998-G-078, Sheet I 10, Rev. 08 2998-G-125, Sheet SI-N-8, Rev. 18

L-2008-266 Attachment 2 Page 26 of 46 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-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-125, Sheet CH-G-1, Rev. 21 2998-G-078, Sheet 120, Rev. 17 2998-G-125, Sheet CH-G-2, Rev. 19 2998-G-078, Sheet 121A, Rev. 31 2998-G-125, Sheet CH-G-3, Rev. 16 2998-G-078, Sheet 122, Rev. 25 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-1 10, Rev. 14 2998-C-124, Sheet CH-I 11, Rev. 11 2998-C-124, Sheet CH- 112, Rev. 13 2998-C- 124, Sheet CH- 129, Rev. 0 2998-C-124, Sheet RC-2, Rev. 13

L-2008-266 Attachment 2 Page 27 of 46 Table 4 Spacer Grid Locations Grid 4 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-2008-266 Attachment 2 Page 28 of 46 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) +/- 5% (Normal)

+/- 14% (Accident) +/- 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 4-85 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.) +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-2008-266 Attachment 2 Page 29 of 46 Table 6

.25. Qnl M

.25 JU.UfC-LOM struc irac plen 4,5 6.5 EA shroud q I 108)

L-2008-266 Attachment 2 Page 30 of 46 T,*hla K - C

L-2008-266 Attachment 2 Page 31 of 46 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-2008-266 Attachment 2 Page 32 of 46 Table 8 (Sheet I 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-2008-266 Attachment 2 Page 33 of 46 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-2008-266 Attachment 2 Page 34 of 46 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-2008-266 Attachment 2 Page 35 of 46 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-2008-266 Attachment 2 Page 36 of 46 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 Al, A2 (psia) BI 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-2008-266 Attachment 2 Page 37 of 46 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 1177 25 1382 28 1104 50 1337 42 1035 62.5 1230 55 943 75 1160 69 829 87.5 1070 83 699 100 948 97 551 112.5 819 110 393 125 680 124 217 137.5 511 138 167 140.6 334 152 165 140.7 184 650 161 141.0 183 700 154 141.4 177 750 146 141.9 170 850 137 291 162 950 127 580 151 1100 116 770 141 1250 105 910 128 1400 91 1000 116 1500 77 1090 101 1600 62 1181 85 1700 45 1271 68 1750 28 1362 49 1850 7 1453 30 1950 0 1548 8 2000 0 2050

L-2008-266 Attachment 2 Page 38 of 46 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 1177 25 1382 28 1104 50 1337 42 1035 62.5 1230 55 943 75 1160 69 829 87.5 1070 83 699 100 948 97 551 112.5 819 110 393 125 680 124 217 137.5 511 138 0 151 334 152 122 165 0 168

L-2008-266 Attachment 2 Page 39 of 46 Table 12 Component Data Required ComponentI Flow Diagram Component Information Pressurizer PORVs V 1474 2998-G-078 Sheet 108 Rev. 5 2998-18810 Rev. 3 V1475 I Pressurizer Safety Valves V1200 2998-G-078 Sheet 109 R18 2998-19690 Rev. 1 V1201 I 2998-19691 Rev. 1 V1202 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. 1 Turbine Stop Valves (Throttle)

FCV-08-640 2998-G-079 Sheet 2, Rev.35 2998-2184 Rev. 10 FCV-08-641 2998-31, Rev 17 FCV-08-642 FCV-08-643

L-2008-266 Attachment 2 Page 40 of 46 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 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. l 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. 1 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 V09158 2998-742 Rev. 2 V3225 2998-G-078 Sheet 132 Rev. 9 2998-19174 Rev. 2 2998-4353 Rev. 5

L-2008-266 Attachment 2 Page 41 of 46 V3624 2998-784 Rev. 6 V3258 2998-655 Rev. 1 V3227 2998-658 Rev. 1 V3215 2998-19174 Rev. 2 2998-4353 Rev. 5 V3614 2998-784 Rev. 6 V3259 2998-655 Rev. 6 V3217 2998-658 Rev. 1 V3245 2998-4353 Rev. 5 2998-19174 Rev. 2 V3644 2998-784 Rev. 6 V3261 2998-655 Rev. 1 V3247 2998-658 Rev. 1 V3235 2998-19174.Rev. 2 2998-4353 Rev 5 V3634 2998-784 Rev. 6 V3260 2998-655 Rev. 1 V3237 2998-658 Rev. 1 FE-3312 2998-G-078 Sheet 131 Rev. 20 HCV-3615 2998-1219 Rev. 9 V3114 2998-655 Rev. 1 V3805 2998-2076 Rev. 19 FE-3311 V3113 2998-19800 Rev. 0 HCV-3616 2998-20356 Rev. 0 2998-20355 Rev. 0 HCV-3617 2998-20356 Rev. 0 2998-20355 Rev. 0 FE-3322 HCV-3625 2998-1219 Rev. 9 V3124 2998-655 Rev. 1 HCV-3626 2998-1218 Rev. 9 FE73321 V3766 8770-14084 Rev. 1 8770-14099 Rev.]

HCV-3627 2998-1218 Rev. 9 FE-3332 HCV-3635 2998-1219 Rev. 9 V3134 2998-655 Rev. 1 FE-3331 V3133 2998-1530 Rev. 5 HCV-3636 2998-1218 Rev. 9 HCV-3637 2998-1218 Rev. 9 FE-3342 V3144 2998-655 Rev. 1 FE-3341 V3143 2998-20097 Rev. 0 HCV-3646 2998-1218 Rev. 9

L-2008-266 Attachment 2 Page 42 of 46 HCV-3647 2998-1218 Rev. 9 V3106 2998-G-078 Sheet 130B Rev. 28 2998-657 Rev. 2 V3206 2998-1024 Rev. 3 FCV-3306 2998-4815 Rev. 7 2998-4816 Rev. 6 FE-3306 V3107 2998-657 Rev. 2 V3207 2998-1024 Rev. 3 FCV-3301 2998-4815 Rev. 7 2998-4816 rev. 6 FE-3301 SO-03-19 V3427 2998-679 Rev. 7 V3656 2998-781 Rev.3 SO-03-20 2998-G-078 Sheet 130A Rev. 19 V3414 2998-679 Rev. 7 V3654 2998-780 Rev.3 V2674 2998-G-078 Sheet 121A Rev. 31 2998-16238 Rev. 0 V2501 2998-3386 Rev. 4 V2118 2998-1036 Rev. 1 V2322 2998-G-078 Sheet 122 Rev. 25 2998-1033 Rev. 0 SS-02-lA 2998-7437 Rev. 3 Suction 2998-9068 Rev. 5 Stabilizer for 2998-9067 Rev. 4 CHG PP 2A Pulsation 2998-9070 Rev. 2 Damper for 2998-9069 Rev. 2 CHG PP 2A V2169 8770-14084 Rev. 1 8770-14099 Rev. 1 V2336 8770-14345 Rev. 1 V2319 2998-1033 Rev. 0 SS-02-IB 2998-7437 Rev. 3 Suction 2998-9068 Rev. 5 Stabilizer for 2998-9067 Rev. 4 CHG PP 2B Pulsation 2998-9070 Rev. 2 Damper 2998-9069 Rev. 2 CHG PP 2B V2168 8770-14084 Rev. 1 8770-14099 Rev. ]

V2464 8770-12770 Rev. I 2998-17048 Rev. 0 V2316 2998-1033 Rev. 0 SS-02-IC 2998-7437 Rev. 3 Suction 2998-9068 Rev. 5 Stabilizer for 2998-9067 Rev. 4 CHG PP 2C Pulsation 2998-9070 Rev. 2 Damper for 2998-9069 Rev. 2

L-2008-266 Attachment 2 Page 43 of 46 CHG PP 2C V2167 8770-14084 Rev. 1 8770-14099 Rev. 1 V2339 2998-1031 Rev. 5 FE-2212 V2429 2998-560 Rev. 2 V2523 2998-2786 Rev. 5 V2462 8770-14084 Rev. 1 8770-14099 Rev. 1 V2535 2998-560 Rev. 2 V2598 2998-15232 Rev. 3 V2485 2998-3487 Rev. 2 V2433 2998-1749 Rev. 3 SE-02-2 2998-18973 Rev. 0 2998-18974 Rev. 0 2998-19677 Rev. 0 2998-19678 Rev. 0 V2484 2998-3487 Rev. 2 V2432 2998-1749 Rev. 3 SE-02-1 2998-18973 Rev. 0 2998-18974 Rev. 0 2998-19677 Rev. 0 2998-19678 Rev. 0 V2593 2998-1009 Rev. 2 V2515 2998-548 Rev. 14 V2516 2998-548 Rev. 14 V2522 2998-G-078 Sheet 120 Rev. 17 2998-2785 Rev. 5 V2341 2998-560 Rev. 2 2998-17024 Rev. 0 V2342 2998-560 Rev. 2 2998-17023 Rev. 0 (Letdown 2998-1611 Rev. 1 Heat Exchanger)

LTDN HT EXCH V2347 2998-557 Rev. 3 2998-17023 Rev. 0 PCV-2201Q 2998-2586 Rev. 6 V2349 2998-4013 Rev. 0 2998-17023 Rev. 0 FE-2202 V2358 2998-1037 Rev. 1 2998-17025 Rev. 0 (Purification 2998-19775 Rev. 0 Filter) 2998-6065 Rev. 3 Purif Filter 2A 2998-16332 Rev. 1 2998-5498 Rev. 4 V2360 2998-1037 Rev. I

L-2008-266 Attachment 2 Page 44 of 46 2998-17025 Rev. 0 V2520 2998-2584 Rev. 6 V2359 2998-590 Rev. 5 2998-17042 Rev. 1 V2370 2998-1029 Rev. 2 (Purification 2998-3642 Rev. 2 Ion Exchanger)

Purif IX 2A V2378 2998-1037 Rev. 1 2998-17025 Rev. 0 V2382 2998-1037 Rev. 1 2998-17025 Rev. 0 V2395 2998-17025 Rev. 0 2998-1037 Rev. 1 (Letdown 2998-5064 Rev. 1 Strainer)

S2900 V2415 2998-17025 Rev. 0 2998-1037 Rev. 1 V2418 2998-17025 Rev. 0 2998-1037 Rev. 1 V2452 2998-17025 Rev. 0 2998-1037 Rev. 1 (Purification 2998-19775 Rev. 0 Filter) 2998-5498 Rev. 4 Purif Filter 2B 2998-6065 Rev. 3 2998-16332 Rev. 1 FE-8011 2998-G-079 Sheet 1, Rev. 41 2998-1420 Rev.6 FE-8021 2998-1421 Rev. 4 2998-2646 Rev. 1 V 1442 2998-G-078 Sheet 109 Rev. 18 2998-3066 Rev. 5 2998-17056 Rev. 0 V 1249 2998-187 Rev. 3 PCV- 11 OOF 2998-546 Rev. 13 V 1444 2998-3066 Rev. 5 2998-17057 Rev. 0 V1477 2998-G-078 Sheet 108 Rev. 5 2998-13278 Rev. 3 V 1479 2998-13277 Rev. 0 V1476 2998-13278 Rev. 3 V1478 2998-13277 Rev. 0 V 1443 2998-G-078 Sheet 109 Rev. 18 2998-3066 Rev. 5 2998-17057 Rev. 0 PCV-II OOE 2998-546 Rev. 13 V1248 2998-187 Rev. 3 V 1441 2998-3066 Rev. 5 2998-17055 Rev. 0 FE-0 1-2 2998-G-078 Sheet 108 Rev. 5 2998-13912 Rev. 1

L-2008-266 Attachment 2 Page 45 of 46 FE-01-1 2998-13912 Rev. 1 FE-09-2A 2998-G-080 Sheet 2B Rev.36 2998-2595 Rev. 2 FE-09-2B 2998-2595 Rev. 2 FE-09-2C 2998-2595 Rev. 2 MV-08-14 2998-G-079 Sheet 1 Rev. 41 2998-10622 Rev. 5 MV-08-15 2998-10622 Rev. 5 MV-08-16 2998-10621 Rev. 6 MV-08-17 2998-10621 Rev. 6 V08359 2998-G-079 Sheet 2 Rev. 35 2998-3012 Rev. 8 V08360 2998-3012 Rev. 8 V09294 2998-G-080 Sheet 2A Rev 43 2998-2143 Rev. 5 V09252 2998-2143 Rev. 5 Table 13 Current Primary Loop Pressure Drop Distribution Geometry AP Geometry AP Friction Station AP Forward Flow Reverse Flow C.urrentV , (_.psi (.Psi)-.....

RV Outlet to SG Outlet 26.92 10.88 9.56 SG Outlet to RV Inlet 1.00 3.62 3.62 RV Outlet to SG Outlet 33.72 13.64 12.00 SG Outlet to RV Inlet 1.24 4.54 4.54

L-2008-266 Attachment 2 Page 46 of 46 REFERENCES

1. St. Lucie Unit 2 UFSAR, Amendment 18.

2. St. Lucie Unit 2 Technical Specifications, Amendment 151.

3. FPL Letter NF-08-224, St Lucie Unit 2 Additional Extended Power Uprate Input Data (EPU AID-2, Rev. 2), dated 6-13-2008.

4, St. Lucie Evaluation PSL-ENG-SEMS-08-045, Revision 01, Extended Power Uprate -HPSI Fathom Model Input Data Request St Lucie Nuclear Plant Unit 2.

5, Deleted.

6. St. Lucie Unit 2 Safety Analysis Plant Parameters (SAPP-2), Revision 10.

7. St. Lucie Unit 1 UFSAR, Amendment 22.

8. Areva Report PMG 545 EFFSL Revision 1

9. St. Lucie Unit 2 Vendor Manual, VTM 2998-10742, Reactor Vessel Internals, Revision 3.

10. St. Lucie Unit 2 Drawing 2998-457, Outline Primary Coolant Pumps, Revision 8.

11. St. Lucie Unit 2 Emergency Procedure 2-EOP-03, Revision 25.

12. St. Lucie Unit 2 Annunciator Procedure 2-ARP-01-J00

13. St. Lucie Evaluation PSL-ENG-SEFJ-05-022, Revision 0.

14. Westinghouse Drawing E-FC 100-F203, Fuel Bundle Grid Cage Assy., Revision 5 (Proprietary)

15. Shaw Stone & Webster Drawing 12915401 -HB(S)-201-2 dated 2/28/08

16. Shaw Stone & Webster Drawing 12915401-HB(S)-209-2 dated 2/28/08

17. Areva Calculation NFPMG DC 106 Revision D

18. Combustion Engineering Drawing E-FG900-1601, Guardian Grid Assembly, Revision 1

19. Westinghouse Letter PCWG-08-33, Rev. 1, "Approval of Revised Category HIP (for Limited Scope Contract) PCWG Parameters for Unit 1 and Revised Category III (for Contract) PCWG Parameters for Unit 2 to Support the EPU Program",

dated 11-4-08.

20. Westinghouse Letter FPL-08-117, "Extended Power Uprate: NRC Data Request",

dated 12-16-08.

21. Westinghouse Letter FPL-08-118, "Extended Power Uprate: NRC Data Request",

dated 12-17-08.