Text

Extended Power Uprate, Data for NRC Confirmatory EPU Analyses
	ML083090048
Person / Time
Site:	Saint Lucie
Issue date:	10/29/2008
From:	Katzman E; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2008-236
	Download: ML083090048 (80)
	v • d • e

0 F=PL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 October 29, 2008 L-2008-236 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. 50-33 5 and 50-3 89 Extended Power Uprate Data for NRC Confirmatory EPU analyses This letter provides data requested by the NRC that is needed to build PSL-specific LOCA models for the NRC's confirmatory EPU analyses. This data is provided in Attachments 1 and 2.

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

Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant ESK/KWF Attachments AOOc)(

an FPL Group company

L-2008-236 Attachnment 1 Page 1 of 37 ST. LUCIE UNIT 1 EPU Input Data Request to NRC for LOCA Model Item Parameter -Description Units Value Comments No.

1.

Plant Operating Conditions la For rated power conditions (Current)

1. Primary and Secondary Flow rates:

IF*,_*

1. 1. Core flow g

4092 Unc: +14,945 gpm and min flow is

gp 410922 365,000 gpm 1.2. Main coolant pumps 95,000 (1A1) gpm96,000 (1 A2)

RCP Pump Test Data 95,000 (1BI) 94,000 (1B2) 1.3. Steam flow lbm/s See Item la.7.1 1.4. Feedwater flow lbm/hr See Item 1a.7.1 1.5. SG recirculation ratio/boiler section flow Power

%Circ Ratio Power-25 15.3 50 8.7

% CircRatio 75 5.95 90 4.9 100 4.3

2.

Primrary and Secondary Pressures:

i

ii '

N N

1.

2. 1 Presurzer sia 250Pressure range is 2225 to 2275, with 2.1.Presurier sia 250Unc:++/-

22 Normal, + 80 Accident 2.2. Core inlet Estimate based on Rx vessel pressure psia 2285 losses of 35.4 psia and core outlet pressure.

L-2008-236 Attachment I Page 2 of 37 Item Parameter -Description Units Value Comments No.

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

2.4. Reactor coolant pump discharge psia 2286 Assume a 1 psi pressure dropfrom pRCP discharge to core inlet.

2.5. Steam generator dome Steam Generator Outlet from psia 863.5 Benchmarked Heat Balance plus pressure drop to Above Primary Deck 2.6. Turbine control valve inlet psia See Item la.7.3 2.7. Detailed primary loop pressure drop distribution psi Later Later

33. Primary and Secondary Temperatures:

,,N.I

,.*N

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

3.2. Cold leg OF 549 Tcold temperature at full power.

Unc: +/- 3°F 3.3. Core outlet OF 599 3.4. Upper Head Assumed to be the same as the core OF 599 outlet temperature since the Rx vessel

4.

Water levels in the pressurizer and steam generators.

de o aeuprha cin

4. 1. Pressurizer

% Tap Span See Figure I1----

4.2. Steam Generators Reference SG elevations from bottom of support skirt base.

L-2008-236 Attachment I Page 3 of 37 Item Parameter -Description Units Value Comments No.

5. Leakage flows (Bypass):

% of vessel flow 3.9 5.1. Outlet nozzle clearances percent 1.18 5.2. Downcomer to upper head percent 0.17 5.3. CEA shrouds Equivalent to a fraction of the leakage percent N/A through guide tubes (item Ia.5.5.1).

This has not been quantified.

5.4. Upper head to upper plenum (guide structure holes) pc 435 Benchar Het b

alance 5.5. Core bypass (guide tubes, barrel-baffle)Het alncTrbn 5.5.p Guide tubes percent 1.86 5.5.2. Barrel-baffle percent 0.50

6.

Steam generator recirculation ratio Pow er-S eI e a.5----

%CircRatio

7.

Heat balance information, such as:

A

7. 1. Feedw ater and steam flow s Ib / r11,851,050 B n h ak d H a a a c 11,784,590 7.2. Feedwater temperature OF 435 Benclhnarked Heat Balance 7..Trieiltpesr Benchmarked Heat Balance, Turbine

L-2008-236 Attachment I Page 4 of 37 Item Parameter -Description Units Value Comments No.

1.

Plant Operating Conditions lb.

For EPU conditions.

1. Primary and Secondary Flow rates:

1. 1. Core flow Nominal value based on the most gpm 410,922 recent measurement. Unc: +/-- 15,000 gpm; TS Min flow is 375,000 gpm 1.2. Main coolant pumps 95,000 (1A1) g 96,000 (1A2)

RCP Pump Test Data 95,000 (1B1) 94,000 (11B2) 1.3. Steam flow Ibm/s See Item lb.7.1 1.4. Feedwater flow lbm/hr See Item lb.7.1

.1.5. SG recirculation ratio/boiler section flow Power-Later Later

% CircRatio

2.

Primary and Secondary Pressures:

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

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

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

2.5. Steam generator dome psia Later Later 2.6. Turbine control valve inlet.

psia See Item lb.7.3 2.7. Detailed primary loop pressure drop distribution psi Later Later

3. Primary and Secondary Temperatures:

3.1. Hot legF Later Assume to be the same as the core outlet temperature since the Rx vessel

L-2008-236 Attachment I Page 5 of 37 Item Parameter -Description Units Value Comments No.

does not have upper head injection.

3.2. Cold leg OF 551 Corresponds to 100% Power. Tcold at Unc: +/- 3F 0% power is 532°F.

3.3. Core outlet OF Later Safety analysis will determnine value during EPU analysis.

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

4.

Water levels in the pressurizer and steam generators.

I 4,

2 4.1. Pressurizer

% Tap Span See Figure 1 4.2. Steam Generators Reference SG elevations from bottom ft 35.0 of support skirt base. Assumes NWL does not change for EPU.

5. Leakage flows (Bypass):

711:..

1/2...

1 >

4 5.1. Outlet nozzle clearances percent 1.27 5.2. Downcomer to upper head percent 0.18 5.3. CEA shrouds percent N/A This has not been quantified.

5.4. Upper head to upper plenum (guide structure percent N/A This has not been quantified holes) 5.5. Core bypass (guide tubes, barrel-baffle) 5.5.1. Guide tubes percent 2.00 Guide and Instrument Tubes 5.5.2. Barrel-baffle percent 0.54 Includes Core Shroud Bypass

6.

Steam generator recirculation ratio Power-

%Circatio See Item lb. 1.5.

7.

Heat balance information, such as:

° N 7.1. Feedwater and steam flows lbm/hr 13,305,870 Draft Heat Balance 13,239,440 7.2. Feedwater temperature OF 436.2 Draft Heat Balance 7.3. Turbine inlet pressure psia 802.5 Draft Heat Balance, 7.3. Turbine inlet pressure psiaI 82.5 Turbine Valve Inlet

L-2008-236 Attachment I Page 6 of 37 Item No.

Parameter -Description Units Value Comments

2.

Analysis Topical Reports

1. Topical Report on the licensing analysis of record for LOCA at rated power and EPU conditions.

-See Comment See Comment le ixere*EIices proviueu urIOw applicable to rated power:

XN-NF-82-49(P)(A), Rev. 1, "Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model",

" EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based",

" EMF-2087(P)(A), "SEM/PWR-98:

ECCS Evaluation Model for PWR LBLOCA Applications".

" EMF-2514, Rev. 0, "St. Lucie Unit 1 Large Break LOCA/ECCS Analysis," Dec. 2000.

For EPU, the SBLOCA Topical Report from above will be used. For LBLOCA, the EPU Topical Report is:

EMF-2103(P)(A), Rev. 0, "Realistic Large Break LOCA Methodology for PWRs".Analysis results are in the I 1TU A D

3.

[Safety System Logic, Setpoints and Delay Times Critical Safety Parameters List (also called "Groundrules document") for the last reload for:

1. ESFAS See Table I I See Table 11 See Fable 11 See Table 11 See Table 11 See Table 11

2.

RPS I 3. SGIS/MSIS See Table 11 See Table 1 See Table II

L-2008-236 Page 7 of 37 Item Parameter -Description Units Value Comments No.

4.

PORV See Table I11 See Table I11 See Table 11

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

4.

Primary and Secondary Pressure Drops

% L

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

2.

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

5.

Core and Fuel Design

1. Number of assemblies N/A 217,----

2.

Dimensions Array: 14 x 14, N/A Pitch: 8.18 in, Length: 157.115 in

3.

Spacer grid locations and K-factors See Table 4 for K-factors Grid locations.

Core inlet region/ bottom grid 3.530 N/A Mid-grid 7 spacers = 8.496 See Comments for Outlet region/top grid = 4.63 K-factors.

Bare rod = 3.971

4.

Vessel pressure drops Current values:

a) 6.8 a) Inlet nozzle & 90 degree turn, psi b) 21.5 b) Downcomer, lower plenum, support c) 7.1 structure & fuel assembly, c) Fuel assembly outlet to outlet nozzle.

5. Bypass and leakage flows

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

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

See Figures 3 and 4 for location.

38,192 total

7.

Number and location of guide tubes 4 guide tubes and 1 N/A instrument tube per See Figure 3 for location.

Assy.

L-2008-236 Attachment I Page 8 of 37 Item No.

Parameter -Description Units Value Comments

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:

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

See Table 6

2.

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

See Table 6

3. Reactor coolant pumps.

See Table 6

4.

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

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

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

7. Main feedwater lines from the isolation valves to the steam generator inlet.

See Table 6

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

9. Safety injection equipment including SITs, high and low pressure injection systems and connecting piping.

10. Charging and letdown system (CVCS).

See Table 6

11. Residual heat removal system.

See Comment See Item 6.9 for LPSI System. LPSI I_

_and RHR are the same system.

L-2008-236 Attachment I Page 9 of 37 Item Parameter -Description Units Value Comments No.

7.

Reactor Vessel Internals uWeight anme area of reactor vessel internalNA/Late 5.s ppruc guides trcueIcue:xasincmestnig

1. Core support barrel Lbs / sq. ft.

90,000 / Later Wet value (Dry weight is 103,000 lbs)

2.

Core shroud Lbs / sq. ft.

31,000 / Later Wet value (Dry weight is 35,000 lbs)

3. Upper and lower core support plates Upper: 18,463 Lbs / sq. ft.

Lower: 12,467

/Later

4.

Fuel alignment plate Lbs / sq. ft.

NA / Later

5. Upper guide structure Includes expansion compensating ring, Lbs / sq. ft.

82,000 / Later fuel alignment plate, upper core plate and CEA shroud.

6. Core support assembly Lbs sq. ft.

42,000 / Later Wet value (Dry weight is 48,000 lbs)

7.

Flow skirt Lbs sq. ft.

2,564 / Later Ib---

8.

Control element assembly (CEA) shroud Lbs sq. ft.

44,418 / Later e

9.

Shroud extensions Lbs /sq. ft.

Later Later

'10. Grid assemblies l

Lbs /sq. ft.

Lae

Later,

8.

Steam Generator Internals of tube sheet exposed to primary side fluid.

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

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

L-2008-236 Attachment I Page 10 of 37 Item Parameter -Description Units Value Comments No.

2.

Weight and surface area of steam generator wrapper.

2.1.Assume height of wrapper is 21.3 ft 2.1.Weigt o SG rappr Im 25955 and material density is 0.284 ibm/in3 2.2. Surface area of SG wrapper ft2 Inner:842 Outer: 850 Assume height of wrapper is 21.3 ft.

tT

9.

Steam Generator Fluid Volumes I1. Inlet plenum Wt 222.026 Including Manway

2.

Outlet plenum Wt 222.665 Including Manway

3. Active tubes, Outlet Inactive Tubes, Inlet Wt 1129.04 (Active),

Inactive Tubes 36.635 (Outlet),

36.635 (Inlet)

4. Number of steam generator tubes N/A 8523

5. Length of shortest and longest tubes ft 50.786 70.981

10.

Steam Generator Parameters s

e

1.

Inventolu r and recirculation ratio versus load (essential at rated power conditions).

arte vabe 3

2.

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

11.

NIS Line Flow Restrictor@l!*'

v

1. Restrictor flow area.

f*36 e

G Ote ozeAe

12.

Steam Generator and Reactor Vessel Heights

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

L-2008-236 Attachment I Page 1 1 of 37 Item Parameter -Description No.

2.

Volume versus height for the reactor vessel with internals installed.

13.

Reactor Coolant Pump Rated Conditions

1. Head ft 273.5

2. Flow gpm 95,000

3. Torque lbf-ft 32,750

4.

Speed rpm 886.25

5. Density lbs/ ft3 Later

6.

Homologous pump curves (four quadrant)

N/A See Table 5

7.

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

8.

Coolant primary system fluid volume within pump Wt 3

112

9.

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

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

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

20 MWt (max)

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

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

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

14.

Core Cooling System

1. HPSI and LPSi delivery curves gpm See Tables 12 & 13

2.

SIT total volume Wt 2020

3.

ITintil resue ndliui vlue si /ft 215 Minimum TS SIT pressure 3.__ SIT initial pressure and liquid volume sia / ft

/ (1090 to 1170)

Nominal liquid volume in Mode 1.

4.

CST minimum capacity gal 110,000

L-2008-236 Attachment I Page 12 of 37 Item Parameter -Description Units Value Comments No.

5.

Charging pump flow versus pressure 40 (nominal) to 49 Recip -rocal pump. Flow is per charging gpm (maximum) pump. Nominal value does not in.clude I

~4 gpm for RCP bleed off.

15.a Control Systems cotoRated powersytmoperationfr of the primary and secondary

--,-,:**°

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

2.

SG pressure (including bypass and ADV)

Later Later Later i3.

Pressurizer heaters and sprays Later Later Later

4.

Pressurizer level Later Later Later

5.

Auxiliary feedwater Later Later Later i6.

CVCS (charging and letdown)

Later Later Later 15.b Control Systems SEPU conditioneoperatirs of the primary and secondaryas______

7.

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

A8.

SG pressure (including bypass and ADV)

Later Later Later

9.

Pressurizer heaters and sprays Later Later Later 1! 0. Pressurizer level Later Later Later 1 1. Auxiliary feedwater Later Later Later S12. CVCS (charging and letdown)

Later Later-Later_

16.1 Reactor Vessel Upper Head

I)*!

1. Upper head fluid temperature at normal operating AF Later temperature Sincehthe saetaRX vessel does I odtos not have upper head injection.

L-2008-236 Attachment I Page 13 of 37 Item Parameter -Description Units Value Comments No.

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:

I. Pressurizer PORVs See Table 2

2.

Pressurizer safety valves See Table 2

3. Main steam safety valves See Table 2

4. Atmospheric dump valves See Table 2

5. TCVs (turbine control valves)

See Table 2

6.

Turbine bypass valves See Table 2

7.

TSVs, (turbine stop valves)

See Table 2

8.

MFIVs See Table 2

9.

MSIVs See Table 2 18 to 20 Reactor Core Parameters 6

1. Control rod insertion versus time after scram.

seconds 3.1 Time for 90% insertion

2.

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

3.

Reactivity versus fuel temperature and reactivity versus

F vs Ap See Tables 7 & 8 moderator density.

4. Moderator temperature coefficient.

F vs Ap See Table 9

5.

Typical top peaked axial power profile.

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

6.

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

L-2008-236 Page 14 of 37 Item Parameter -Description Units Value Comments No.

7.

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

8.

Gap conductance.

Later Later Later

9.

Linear heat rate.

Value of 6.96 assumes 100 SS rods.

kW / ft 15.0 (Max)

Without this assumption, the average is 6.96 Ave) 6.94 kW/ft.

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

21.

Operator Actions During LOCA

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

Accident analysis assumes LOOP automatic or manual)

Pumps concurrent with LOCA, and pumps are None automatically trip not loaded onto EDGs or manually on LOOP 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

Pressurizer level is at least 30%

and NOT lowering,

At least ONE S/G is available for None See Comment RCS heat removal with level being restored to or maintained between 60 and 70% NR,

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

L-2008-236 Attachment I Page 15 of 37 Item Parameter -Description Units Value Comments No.

assumption for EPU analysis.

3.

MS line break auxiliary feedwater control.

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

Most recent COLR provided to NRC

22.

Core Operating Limits Report See Comment See Comment 7-0 EPl LR2to7be6provided 27-2007. 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, etc.):***N

t*IiNN*

N*!*

1. Density Later Later Later

2.

Specific heat Later Later Later

3.

Thermal conductivity "Later Later Later

4.

Emnissivity versus temperature Later Later Later

L-2008-236 Page 16 of 37 Figure 1 PRESSURIZER LEVEL PROGRAM 100.0 80.0 CL CL w

F-

.N.

W.

60.0 40.0 20.0 0.0 +-

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

L-2008-236 Attachment I Page 17 of 37 Fianre 2 -

I- -

W U

.2

-I 1Ic Note: This curve represents current analysis.

L-2008-236 Attachment I Page 18 of 37 I

-1T-

ýEACTOR CORG CROSS-SEC~TiON

L-2008-236 Page 19 of 37

L-2008-236 Attachment I Page 20 of 37 Table 1 Volume vs. Height for the Reactor Vessel with Internals Installed.

Region Elevation Volume vs. Height Volume (ft)

(ft3 per ft)

(ft3 )

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

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

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

12.8 69.7 892 V4)

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

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

L-2008-236 Page 21 of 37 Table 2 Component Data Required Component Flow Diagram Component Information Pressurizer PORVs V1402 8770-G-078 Sheet 1 A, Rev 30 8770-9676 Rev 1 V1404 8770-9677 Rev 2 8770-9678 Rev 1 8770-9679 Rev 2 8770-9680 Rev 4 8770-9681 Rev 7 8770-9682 Rev 2 8770-9683 Rev I Pressurizer Safety Valves V1200 8770-G-078 Sheet 110A, Rev 30 8770-13730, Rev 1 V1201 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 I HCV-08-2B 8770-8971, Rev 1 Turbine Control Valves (Governor)

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

L-2008-236 Attachment I Page 22 of 37 Component Flow Diagram Component Information FCV-08-646 8770-116, Rev 24 FCV-08-647 Turbine By-Pass Valves PCV-8801 8770-G-079, Sheet 2, Rev. 45 8770-2082, Rev 10 PCV-8802 8770-2083, Rev 11 PCV-8803 PCV-8804 PCV-8805 Turbine Stop Valves (Throttle)

FCV-08-640 8770-G-079, Sheet 2, Rev. 45 8770-103, Rev 7 FCV-08-641 8770-115, Rev 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 1

1 8770-14211, Rev 0 Main Steam Isolation Valves HCV-08-1A 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 8770-8951, Rev 2 8770-8952, Rev 0 8770-9673, Rev 10 8770-9674, Rev 8 Miscellaneous Components V2526 V2501 V2118 V2623 V2500 V2101 V2322 SS (Suction Stabilizer for Charging Pump I C)

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

PD (Pulsation Damper on CHG PP IC) 8770-G-078 Sheet 121A Rev. 38 8770-G-078 Sheet 120B Rev 17 8770-1380, Rev. 7 8770-1589, Rev. 9 8770-2699, Rev 2 8770-853, Rev 1 8770-1589, Rev 9 8770-1592 Rev. 10 8770-9301 Rev. 1 8770-9302 Rev. 5 8770-205 Rev. 0 8770-364 Rev. 4 8770-12137 Rev. 5 8770-12138 Rev. 0 8770-9982 Rev. 1 8770-9981 Rev. I

L-2008-236 Attachment I Page 23 of 37 Component [

Flow Diagram

[

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

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

CHG PP 1B (Charging Pump 1B)

PD (Pulsation Damper on CHG PP 1B)

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

CHG PP IA (Charging Pump IA)

PD (Pulsation Damper on CHG PP IA)

V2339 V02132 V2338 SE-02-2 8770-14099 Rev. 1 8770-14084 Rev. 1 8770-14345 Rev. 1 8770-9379 Rev. 1 8770-2310 Rev. 0 8770-1588 Rev. 5 8770-1571 Rev. 8 8770-10468 Rev. 0 8770-420 Rev. 2 8770-1592 Rev. 10 8770-9301 Rev. 1 8770-9302 Rev. 5 8770-12137 Rev. 5 8770-205 Rev. 0 8770-364 Rev. 4 8770-12138 Rev. 0 8770-9982 Rev. 1 8770-9981 Rev. 1 8770-14084 Rev. 1 8770-14099 Rev. 1 8770-14345 Rev. 1 8770-9379 Rev. 1 8770-1592 Rev. 10 8770-9301 Rev. 1 8770-9302 Rev. 5 8770-12137 Rev. 5 8770-364 Rev. 4 8770-12138 Rev. 0 8770-205 Rev. 0 8770-14345 Rev. 1 8770-9378 Rev. 0 8770-10883 Rev. 2 8770-1588 Rev. 5 8770-12507 Rev. 0 8770-12508 Rev. 0

L-2008-236 Attachment I Page 24 of 37 Component Flow Diagram Component Information V2433 SE-02-1 V2432 V2519 V2515 V2516 V2341 LCV-2110P V2342 LTDN (Letdown Heat Exchanger)

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

V2360 V2520 V2369 V2370 V2378 V2382 V2395 S2900 V2415 V2418 Purif FLTR 1B (Purification Filter 1B)

V2452 FE-801 1 FE-8021 2998-19678 Rev. 0 2998-19677 Rev. 0 8770-14084 Rev. 1 8770-14099 Rev. 1 8770-12507 Rev. 0 8770-12508 Rev. 0 2998-19677 Rev. 0 8770-1570 Rev. 10 8770-926 Rev. 13 8770-858 Rev. 2 8770-928 Rev. 8 8770-860 Rev. 4 8770-928 Rev.. 8 8770-860 Rev. 4 8770-1588 Rev. 5 8770-16166 Rev. 0 8770-787 Rev. 4 8770-1588 Rev. 5 8770-419 Rev. 2 8770-G-078 Sheet 120A Rev. 023 8770-G-079, Sheet 1, Rev. 53 8770-1578 Rev. 4 8770-971 Rev. 9 8770-1591 Rev. 5 8770-2301 Rev. 1 8770-1592 Rev. 10 8770-14147 Rev. 1 8770-558 Rev. 3 8770-8852 Rev. 2 8770-8617 Rev. 3 8770-1592 Rev. 10 8770-853 Rev. 1 8770-1592 Rev. 10 8770-1589 Rev. 9 8770-1592 Rev. 10 8770-1592 Rev. 10 8770-1592 Rev. 10 8770-1480 Rev. 1 8770-1592 Rev. 10 8770-1592 Rev. 10 8770-14147 Rev. 1 8770-558 Rev. 3 8770-8852 Rev. 2 8770-8617 Rev. 3 8770-1592 Rev. 10 8770-965, Rev 5 8770-965, Rev 5

L-2008-236 Page 25 of 37 Component I Flow Diagram I

Component Information V09252 V09294 AFW PP AFW PP IA lB AFW PP 1C V09139 V09140 FE-09-2C MV-09-1 1 MV-09-12 V09151 V09157 V09152 V09158 V09123 V09107 V09108 V09124 FE-09-2A FE-09-2B MV-09-9 MV-09-10 V09119 V09135 V09120 V09136 V 1403 V1405..

V 1406 V 1407 PZR Quench Tank V 1252 V1253 PCV-1 1OOE PCV-1OOF V1248 V 1249 V1250 V1251 SO-03-13 SO-03-14 8770-G-080, Sheet 3, Rev 54 8770-G-080, Sheet 4, Rev. 41 8770-G-078 Sheet 1OA, Rev 30 8770-G-078 Sheet 130A, Rev 27 8770-5736, Rev 4 8770-7139, Rev 3 8770-3044, Rev 3 8770-4409, Rev 0 8770-15879, Rev 0

8770-3183, Rev 7 8770-4408, Rev 0 8770-1398, Rev 6 8770-1257, Rev 3 8770-3544, Rev 0 8770-3294, Rev 4 8770-6967, Rev 5 8770-6967, Rev 5 8770-3775, Rev 6 8770-3775, Rev 6 8770-3774, Rev 3 8770-125 1, Rev 2 2998-20110, Rev 1 8770-3775, Rev 6 8770-1251, Rev 2 8770-1251, Rev 2 8770-3294, Rev 4 8770-3544, Rev 0 8770-6966, Rev 5 8770-6966, Rev 5 8770-3775, Rev 6 8770-3775, Rev 6 8770-3774, Rev 3 8770-125 1, Rev 2 8770-1374, Rev 10 8770-1374, Rev 10 8770-1750, Rev 5 8770-1750, Rev 5 8770-898, Rev 3 8770-1769, Rev 4 8770-1769, Rev 4 8770-864, Rev 2 8770-970, Rev 15 8770-6586, Rev 3 8770-6777, Rev 1 8770-16184, Rev 0 8770-1769; Rev4 4 8770-16184, Rev 0 8770-1769, Rev 4

L-2008-236 Page 26 of 37 Component Flow Diagram Component Information SO-03-15 V3427 V3405 V3414 V3654 V3656 HCV-3616 HCV-3626 HCV-3636 HCV-3646 V3113 V3123 V3133 V3143 FE-3311 FE-3321 FE-3331 FE-3341 HCV-3615 HCV-3625 HCV-3635 HCV-3645 V3114 V3124 V3134 V3144 FE-3312 FE-3322 FE-3332 FE-3342 HCV-3617 HCV-3627 HCV-3637 HCV-3647 V3106 V3107 V3206 V3207 FCV-3306 FE-3306 8770-G-078 Sheet 131A, Rev 27 8770-G-078 Sheet 130B, Rev 31 8770-1768, Rev 8 8770-1768, Rev 8 8770-1768, Rev 8 8770-1377, Rev 6 8770-1377, Rev 6 8770-1376, Rev 5 8770-1376, Rev 5 8770-1376, Rev 5 8770-1376, Rev 5 8770-12709, Rev 10 8770-1570, Rev 10 8770-1570, Rev 10 8770-1570, Rev 10 8770-1375, Rev 6 8770-1375, Rev 6 8770-1375, Rev 6 8770-1375, Rev 6 8770-1748, Rev 7 8770-1748, Rev 7 8770-1748, Rev 7 8770-1748, Rev 7 8770-2301, Rev 1 8770-2301, Rev 1 8770-2301, Rev 1 8770-2301, Rev 1 8770-1376, Rev 5 8770-1376, Rev 5 8770-1376, Rev 5 8770-1376, Rev 5 8770-3646, Rev 1 8770-3646, Rev 1 8770-9348, Rev 3 8770-9348, Rev 3 8770-861, Rev 2 8770-930, Rev 8 8770-2301, Rev 1

L-2008-236 Attachment I Page 27 of 37 Table 3 Secondary Side Volume per Unit Height ( ftIft) s 1.5111211

.7.98 4.8679 178.1580 39.240

-32,563 SO.191

-22.271:

-18 802

-15.333 11.885 4.927 2.0 0

FfT ASOVE T/S

SEC, FACE (F-t) 6 7.227

-129.294' 5S2.28S 10.178-

~-37.679

-210.801

-70.432

-70.4q32

- 70.132

- 70. 432 89.8a29 70,345

+

282.671 278.779

- 277. 829

-164.980

-2.27.047

-60.610 80.007

-80.523 DOWNC01MER, RISER OA TOTAL

L-2008-236 Page 28 of 37 Table 4 Spacer Grid Locations Grid #

Distance (in) 1 6.302 2

18.185 3

36.797 4

55.656 5

74.515 6

93.374 7

112.233 8

131.092 9

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

L-2008-2'36 Attachment I Page 29 of 37 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

-3.245

-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 0.8.10

-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-2008-236 Page 30 of 37 Table 6 Unit 1 Piping Isometric Drawings by P&ID Flow Diagram Isometric/Component Drawing Reactor Vessel 8770-G-078, Sheet 10OB, 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 10B, Rev. 26 8770-39, Rev 3 8770-40, Rev 3 8770-530, Rev 3 8770-781, Rev 3 8770-880, Rev I 8770-1496, Rev 2 Reactor Coolant Pumps 8770-G-078, Sheet I11A, Rev. 15 8770-15, Rev 8 8770-G-078, Sheet 11 IB, Rev. 15 8770-178, Rev 11 8770-G-078, Sheet 11 IC, Rev. 14 8770-54, Rev 9 8770-G-078, Sheet I11D, Rev. 16 Steam Generators 8770-G-078, Sheet I IOB, Rev. 26 8770-13348, Rev 1 8770-G-080, Sheet 3, Rev. 54 8770-G-079, Sheet 1, Rev. 53 Pressurizer/Surge Line/Spray Lines/Relief Lines 8770-G-078, Sheet 11OA, Rev. 30 8770-G-125 Sheet RC-AB-1, Rev 3 8770-15377, Rev 0 8770-15287, Rev 0 8770-15307, Rev 0 8770-16184, Rev 0 8770-1658, Rev 0 8770-15820, Rev 0 8770-6624, Rev 2 8770-15298, Rev 0 8770-15819, Rev 0 8770-B-124 Sheet RC-187, Rev 1

L-2008-236 Attachment I Page 31 of 37 Main Steam Lines Out to the Turbine Stop Valves 8770-G-079, Sheet 1, Rev. 53 8770-G-125, Sheet MS-L-1, Rev 6 8770-G-079, Sheet 2, Rev. 45 8770-G-125, Sheet MS-L-6, Rev 6 Main Feedwater Lines from the Isolation Valves to the Steam Generator Inlet 8770-G-080, Sheet 3, Rev. 54 8770-G-125, Sheet BF-M-06, Rev 4 Auxiliary Feedwater Lines 8770-G-080, Sheet 4, Rev. 41 8770-G-125, Sheet BF-M-07, Rev 6

_8770-G-125, Sheet BF-M-08, Rev 10 Safety Injection 8770-G-078, Sheet 130A, Rev. 27 8770-G-125, Sheet SI-N-5, Rev 2 8770-G-078, Sheet 130B, Rev. 31 8770-G-125, Sheet SI-N-6, Rev 4 8770-G-078, Sheet 131A, Rev. 27 8770-G-125, Sheet SI-N-7, Rev 3 8770-G-078, Sheet 131B, Rev. 19 8770-G-125, Sheet SI-N-8, Rev 4 8770-G-125, Sheet SI-N-10, Rev 3 8770-G-125, Sheet SI-N-12, Rev 2 8770-B-124 Sheet SI-27 Rev 13 8770-B-124 Sheet SI-28 Rev 12 8770-B-124 Sheet SI-29 Rev 12 8770-B-124 Sheet SI-30 Rev 11 8770-B-124 Sheet SI-31 Rev 13 8770-B-124 Sheet SI-32 Rev 9 8770-B-124 Sheet SI-33 Rev 14 8770-B-124 Sheet SI-34 Rev 10 8770-B-124 Sheet SI-128 Rev 1 8770-B-124 Sheet SI-129 Rev 3 8770-B-124 Sheet SI-130 Rev 4 8770-B-124 Sheet SI-131 Rev 2 Charging and Letdown System (CVCS) 8770-G-078, Sheet 1 10B, Rev. 26 8770-G-078, Sheet 120A, Rev. 23 8770-G-078, Sheet 120B, Rev. 17 8770-G-078, Sheet 121A, Rev. 38 8770-G-078, Sheet 121B, Rev. 32 8770-G-088, Sheet 1, Rev. 51 8770-G-125 Sheet CH-G-1 Rev. 2 8770-G-125 Sheet CH-G-2 Rev 1 8770-G-125 Sheet CH-G-3 Rev 4 8770-G-125 Sheet CH-G-4 Rev 0 8770-G-125 Sheet CH-G-5 Rev 0 8770-G-125 Sheet CH-G-8 Rev 2 8770-G-125 Sheet CH-G-9 Rev 4 8770-G-125 Sheet CH-G-12 Rev 6 8770-G-125 Sheet CH-G-13 Rev I 8770-B-124 Sheet CH-1 Rev 2 8770-B-124 Sheet CH-2 Rev 2 8770-B-124 Sheet CH-3 Rev 3 8770-B-124 Sheet CH-4 Rev 4 8770-B-124 Sheet CH-9 Rev 8 8770-B-124 Sheet CH-37 Rev 2

L-2008-236 Page 32 of 37 8770-B-124 Sheet CH-43 Rev 5 8770-B-124 Sheet CH-63 Rev 7 8770-B-124 Sheet CH-64 Rev 5 8770-B-124 Sheet CH-65 Rev 12 8770-B-124 Sheet CH-66 Rev 9 8770-B-124 Sheet CH-68 Rev 10 8770-B-124 Sheet CH-69 Rev 8 8770-B-124 Sheet CH-70 Rev 7 8770-B-124 Sheet CH-71 Rev 6 8770-B-124 Sheet CH-72 Rev 8 8770-B-124 Sheet CH-74 Rev 12 8770-B-124 Sheet CH-75 Rev 7 8770-B-124 Sheet CH-77 Rev 10 8770-B-124 Sheet CH-78 Rev 5 8770-B-124 Sheet CH-79 Rev 8 8770-B-124 Sheet CH-80 Rev 14 8770-B-124 Sheet CH-82 Rev 21 8770-B-124 Sheet CH-92 Rev 11 8770-B-124 Sheet CH-124 Rev 11 8770-B-124 Sheet CH-125 Rev 7 8770-B-124 Sheet CH-126 Rev 8 8770-B-124 Sheet CH-128 Rev 5 8770-B-124 Sheet CH-129 Rev 8 8770-B-124 Sheet CH-130 Rev 6 8770-B-124 Sheet CH-141 Rev 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 I 8770-B-124 Sheet CH-188Rev 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-2008-236 Page 33 of 37 Table 7. TEMPERATURE vs. DOPPLER REACTIVITY WORTH Current Analysis Value EPU Analysis Value FUEL TEMPERATURE DOPPLER REACTIVITY FUEL TEMPERATURE DOPPLER REACTIVITY (OF)

(Ap)

(OF)

(Ap) 0.0 0.0*

250.0 0.0 400.0

-0.0037338 667.5

-0.0098574 808.1

-0.0128639 No changes from current No changes from current 946.5

-0.0156432 analysis analysis 1077.9

-0.0181490 1199.1

-0.0203649 1309.0

-0.0222887 1445.5

-0.0246159 5000.0

-0.0246159**

Notes:

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

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

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

DENSITY (Ibm/ft 3)

REACTIVITY (Ap)

DENSITY (Ibmrfte)

-0.350 0.0 No changes from current No changes from current

-0.270 2.1 analysis analysis

-0.190 5.0

-0.100 10.0

-0.090 12.1

-0.060 15.0

-0.030 20.0

-0.020 22.1

-0.012 25.0

-0.005 30.0

-0.0001 32.1

-0.0000 35.0

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

Reactivity corresponding to the most positive MTC @ HFP, BOC

L-2008-236 Page 34 of 37 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 450.0 0.03959 No changes from No changes from 450.0 0.03959 current analysis.

current analysis.

532.0 0.01627 572.0**

0.0000**

Notes:

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

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

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

(FPL)

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

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-2008-236 Attachment I Page 35 of 37 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 > 111 OF but < 2000F.

RPS S/G Level Lo 21.0%

> 20.5%

+/- 3% (Normal)

+/- 5% (Normal)

Current cycle safety analysis parameter document

+/- 14% (Accident)

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

RPS RCS Low Flow

> 95% Design Flow 3.5%

4%

SIAS/CIS Cont. Press Hi 4.375 psig

< 5.0 psig

+/- 1.3 psi

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

< 10.0 psig

+ 1.3 psi

+/- 1.3 psi SIAS PZR Press Lo 1612.5 psia

> 1600 psia

+ 22 psi (Normal)

+/- 40 psi (Normal)

+/- 80 psi (Accident)

MSIS S/G Press Lo 600 psig

_ 585 psig

+ 32 psi (Normal)

+ 40 psi (Normal)

Current cycle safety analysis parameter document

+/- 80 psi (Worst Normal) includes a target analysis value of+4 80 psi (Worst Normal). Worst Normal is defined as Containment Temperature > Il 1 OF 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 > 1 1OF but < 200'F.

AFAS FW Press DP Hi 142.5 psid

< 150.0 psid Not specified

< 245 psid (setpoint)

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

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

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

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

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

Current cycle safety analysis parameter document 1040 psia (nominal) 3% (accumulation) 3% (accumulation) includes a target analysis value of+/- 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-2008-236 Page 36 of 37 TABLE 12 ST. LUCIE UNIT 1 - HIGH PRESSURE SAFETY INJECTION PUMP DELIVERY FLOWIPUMP DEGRADED PUMP NON-DEGRADED PUMP MINIMUM NOMINAL NOMINAL MAXIMUM 4-LOOP 3-LOCP 4-LOOP 3-LOCP RCS 4-LOOP LOWEST TOTA MINIMU RCS 4-LOOP HIGHEST TOTA MAXIMU PRESSURE TOTAL 3-LOOPS PRESSURE TOTAL 3-LOOPS MIN ANALYSIS MAX ANALYSIS (psia)

(gpm)

(psia)

(gpm)

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

0 0

0 1162 250 200 276 221 1215 0

0 0

0 1251 168 134 200 160 1265 0

0 0

0 1303 89 72 138 110

L-2008-236 Attachment I Page 37 of 37 Table 13. ST. LUCIE UNIT 1 - LOW PRESSURE SAFETY INJECTION PUMP DELIVERED

" Min Degraded LPSI Flow/Pump (4 Valves)

I Max LPSI Flow/Pump (4 Valves)

I Max LPSI Flow with Two Pumps (4 Valves)

Min Degraded LPSI Flow/Pump (2 Valves) I RCS TOTAL 3-LOOP PRESSURE FLOW MINIMUM (PSIA)

(GPM)

(GPM) 144.44 0

0 1.44.42 61 45 144.29 161 119 143.22 461 340 141.54 711 525 138.92 961 709 134.83 1211 894 129.61 1461 1078 123.24 1712 1263 115.69 1962 1447 106.95 2212 1632 96.99 2463 1817 85.78 2713 2002 73.31 2964 2187 44.47 3466 2557 10.30 3968 2927 RCS TOTAL 3-LOOP PRESSURE FLOW MAXIMUM (PSIA)

(GPM)

(GPM) 202.48 0

0 202.46 56 43 202.34 1.56 119 201.30 456 348 199.65 706 540 197.01 956 731 192.68 1206 922 187.10 1456 1114 180.25 1706 1305 172.10 1957 1497 162.61 2207 1688 151.76 2458 1880 139.52 2708 2071 125.86 2959 2263 94.14 3461 2647 56.39 3963 3031 RCS TOTAL 3-LOOP PRESSURE FLOW MAXIMUM (PSIA)

(GPM)

(GPM) 202.48 0

0 202.41 111 85 201.96 311 238 198.03 911 697 191.81 1411 1079 182.62 1911 1462 169.77 2412 1844 153.70 2912 2227 134.38 3413 2610 111.78 3913 2993 85.86 4414 3376 56.60 4915 3759 23.96 5416 4143 17.02 5517 4219 RCS TOTAL 1-LOOP PRESSURE FLOW MINIMUM (PSIA)

(GPM)

(GPM) 144.44 0

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

L-2008-236 Page 1 of 42 ST. LUCIE UNIT 2 EPU Input Data Request to NRC for LOCA Model Item Parameter -Description Units Value Comments No.

1.

Plant Operating Conditions l a.

For rated power conditions (Current):

1. Primary and Secondary Flow rates:

1. 1. Core flow gpm 412,000

/Unc:350. + 14,500 gpmn and rain flow is 1.2. Main coolant pumps 97,500 (2A1) g 96,000 (2A2)

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

%CircRatio 70 5.42 90 3.96 100 3.46

2.

Primary and Secondary Pressures:

2.1. Pressurizer Nominal Operating Pressure is 2250 psia 2250 psia. Pressure range is 2225 to 2275, with Unc: + 45 Normal, + 90 Accident.

L-2008-236 Page 2 of 42 Item Parameter -Description Units Value Comments No.

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

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

2.4. Reactor coolant pump discharge 2Assume a I psi pressure drop from RCP rpsia 2287 discharge to core inlet.

2.5. Steam generator dome SG outlet pressure from benchmark heat psia 886.81 balance plus dP to upstream of flow restrictor 2.6. Turbine control valve inlet psia See Item Ila 7.3 2.7 Detailed primary loop pressure drop distributionpsLaeLtr

3.

Primary and Secondary Temperatures:

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

3.2. Cold leg OF 549 Tcold temperature at full power.

Unc: +/- 3YF 3.3. Core outlet Based on Tcold of 549F and Tave of 574.5F.

3.4. Upper Head Assumed to be the same as the core OF 600 outlet temperature since the Rx vessel

.does not have upper head injection....

4.

Water levels in the pressurizer and steam generators, 4.1. Pressurizer

% Tap Span See Figure 1

L-2008-236 Page 3 of 42 Item Parameter -Description Units Value Comments No.

4.2. Steam Generators in 411.3 Level above tubesheet

5. Leakage flows (Bypass):

% of vessel flow 3.7 This is the total core bypass maximum value for minimum core flow rate.

5.1. Outlet nozzle clearances Assume bypass breakdown documented percent 1.12 in Unit I UFSAR due to unit similarities.

5.2. Downcomer to upper head Assume bypass breakdown documented percent 0.16 in Unit I UFSAR due to unit similarities.

5.3. CEA shrouds Equivalent to a fraction of the leakage percent N/A through guide tubes (item I a.5.5. 1).

This has not been quantified.

5.4. Upper head to upper plenum (guide structure h

t b ane holes)pecnN/Thshsntbequnied 5.5. Core bypass (guide tubes, barrel-baffle) 5.5. 1. Guide tubes Assume bypass breakdown documented percent 1.76 in Unit I UFSAR due to unit similarities.

5.5.2. Barrel-baffle Assume bypass breakdown documented

-percent 0.47 in Unit I UFSAR due to unit similarities.

6.

Steam generator recirculation ratio Power-S eIe a15----

%CircRatio

7.

Heat balance information such as.:

-7

7. 1. Feed and steam fl ow s Ib / r11,905,010 B n h a k H a a a c 11,806,740 7.2. Feedwater temperature OF 435 Benchmark Heat Balance

L-2008-236 Page 4 of 42 Item Parameter -Description Units Value Comments No.

7.3.Turine nle presur.

psa 82.7Benchmark Heat Balance, Turbine Inlet 7.3.Turine nle presur, psa 82.7Valve

1.

Plant Operating Conditions lb.

For EPU conditions.

1. Primary and Secondary Flow rates:

[

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

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

RCP Pump Test Data gpm 95,000 (2B 1) 94,000 (2B2) 1.3. Steam flow Ibm/s See Itemlb 7.1 1.4. Feedwater flow lbm/hr See Item lb 7.1 1.5. SG recirculation ratio/boiler section flow Power

%Circ Power-Ratio 25 13.86

%CircRatio 50 76 75 4.40 109 3.02

2. Primary and Secondary Pressures (absolute i' pressures):

t

2. 1. Pressurizer Range: 2225 to 2275 psia.

psia 2250 Unc.: + 45 psi normal,

+ 90 psi harsh.

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 2.6. Turbine control valve inlet psia See Item lb.7.3

L-2008-236 Page 5 of 42 Item Parameter -Description Units Value Comments No.

2.7 Detailed primary loop pressure drop psi Later Later distribution

3. Primary and Secondary Temperatures:

3.1. Hot leg OF Later Safety analysis will determine value during EPU analysis.

3.2. Cold leg OF 551 Corresponds to 100% Power. Tcold at Unc: +/- 3F zero power is 532F.

3.3 Core outlet OF Later Safety analysis will determine value during EPU analysis.

3.4 Upper Head Assume to be the same as the core OF Later outlet temperature since the Rx vessel does not have u er head iniection.

4.

Water levels in the pressurizer and steam generators I

2 4.1. Pressurizer

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

5. Leakage flows:

% of vessel flow 3.7 5.1. Outlet nozzle clearances

.t Assumed to be similar to current 5spercent 1.12 operating value.

5.2. DC to upper head p0.16 Assumed to be similar to current apercent operating value.

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

5.4. Upper head to upper plenum (guide structure hoe)percent N/A.

This has not been quantified.

holes) 5.5.

Core bypass (guide tubes, barrel-baffle) 5.5.1. Guide tubes p1.76 Assumed to be similar to current percent operating value.

5.5.2. Barrel-baffle pAssumed to be similar to current epercent 0.47 operating value.

6.

Steam generator recirculation ratio Power-.

See Item lb 1 5

%CircRatio

7.

Heat balance information such as:

7.1 Feedwater and steam flows lbm/hr 13,345,230 Draft Heat Balance

L-2008-236 Page 6 of 42

Item Parameter -Description Units Value Comments No.

13,246,890 7.2 Feedwater temperature OF 436.1 Draft Heat Balance 7.3 Turbine inlet pressure.

psia 853.1 Draft Heat Balance, Turbine Inlet Valve

2.

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

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

1. Topical Report on the licensing analysis of LOCA Evaluation Model", March record for LOCA at rated power and EPU See Comment See Comment 2001.

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

A, "Calculative Method for the ABB CE Small Break LOCA Evaluation Model", "April 1998.

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

3.

Safety System Logic, Setpoints and Delay Times Critical Safety Parameters List (also called "Groundrules document") for the last reload for:

See I.

ESFAS See Table 5 See Table 5 See Table 5

2.

RPS See Table 5 See Table 5 See Table 5

3.

SGIS/MSIS See Table 5 See Table 5 See Table 5

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

5.

SRV.

See Table 5 See Table 5 See Table 5

L-2008-236 Pane 7 of 42 Item Parameter -Description ts Value Comments No.

4.

Primary and Secondary Pressure Drops

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

2.

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

5.

Core and Fuel Design

1. Number of assemblies N/A

.217

2. Dimensions Array: 16 x 16, The pitch is the sum of 7.972 and 0.208 N/A Pitch: 8.180 in, 8.180 in.

Length: 158.5 in

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

4.

Vessel pressure drops Current values:

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

5. Bypass and leakage flows

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

above

6. Number and location of fuel rods.

236 per assy 51,212 total.

Some fuel rods contain burnable N/A See Figs. 3 and 4 absorber material.

below for location.

7.

Number and location of guide tubes.

5 guide tubes per assy.

N/A See Fig. 3 below for location.

L-2008-236 Page 8 of 42 Item No.

Parameter -Description Units Value Comments

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 formn 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, including upper plenum or head to downcomer, if available).

See Table 3

2.

Primary loop piping (hot leg, cold leg, pump suction)

See Table 3

3. Reactor coolant pumps See Table 3

4.

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

5.

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

6. Main steam lines out to the turbine stop valves, including safety and relief valves and connecting See Table 3 lines, main steam isolation valves, flow restrictors, etc.

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

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

9.

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

10. Charging and letdown system (CVCS).

See Table 3

11. Residual heat removal system.

See Comments See Item 6.9 for LPSI System. LPSI

L-2008-236 Page 9 of 42 Item Parameter -Description Units Value Comments No.

and RHR are the same system.

7.

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

1. Core support barrel Lbs / sq. ft.

136,600 /Later Dry weight. Wet weight equals to 119,500 lbs.

5.

Upprgue s truu r

/sq.ft.

33Dry weight. Wet weight equals to 2.Cr hodLbs

/ sq. ft.

122,200 / Later shrouds andshru.xesos e

wegt9 qalo60,00 lbs.

3. Uperandlowr cre sppot pate Lb / s.

Lter/ Lter Lower core plate included below for

6.

CoresUpport a

sslowermblyesuppor a

Lbs / sq. ft.

4 0 / Later Dweight of core support assy.

4.

Fuel alignment plate Lbs / sq. ft.

Later / Later

5. Upper guide structure Dry weight. Includes the FAP, CEA Lbs / sq. ft.

122,200 /Later shrouds and shroud extensions. Wet weight equals to 106,900 lbs.

6

2.

WoreigpofS wra r

Ib 3.45,70 I

sDry weight. Includes the lower core

6. Cre upprt sseblyLbs sq ft 45500/ Lter plate. Wet weight equals to 39,800 lbs.

7.

Flow skirt Lbs / sq. ft.

5,0001/ ---

Identified as flow baffle.

8. Control element assembly (CEA) shrouds Lbs / sq. ft.

Later / Later--

9.

Shroud extensions Lbs / sq. ft.

Later / Later

10. ridasseblis Lb / q. t.

1 pe Ass /LterTop grid = 2 lbs, 8 spacers @ 1.8 lbs

10. ridasseblis Lb / q. f.

1 perAss

/ Ltereach. bottom grid = 2.6 lbs..

8.

Steam Generator Internals I1. Weight of steam generator tube sheet and surface

[

area of tube sheet exposed to primary side fluid.

1. 1 Weiht o Tue Shet Im 93230Weight with integral forged lower.

1.1.Weigt o Tub Shet Im 93230cylindrical ring and cladding 1.2. -Surface area of Tube Sheet (Primary Side) ft2 Later Later

2.

Weight and surface area of steam generator wrapper.

1

2. 1. Weight of SG wrapper I

lbm 34,730

[Includes wrapper roof

L-2008-236 Page 10 of 42 Item Parameter -Description Units Value Comments No.

2.2. Surface area of SG wrapper 122 Later Later

9.

Steam Generator Fluid Volumes

1. Inlet plenum 123 338.4 Includes Manway

2. Outlet plenum W2 332.0 Includes Manway

3. Active and inactive W2 1230.0 (within tube sheet) tubes 41.3

4. Number of steam generator tubes 8999

5. Length of shortest and longest Later Later

10.

Steam Generator Parameters Vessel Heights

1. Inventory and recirculation ratio versus load (essential ators ted power conditions)

2.

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

11.

MS Line Flow Restrictor 3.791 to 3.803 perOultNzeAra

1. Restrictor flow area 1t2 SG,OultNzeAra 2.27 er SG Flow Venturi Area

12.

Steam Generator and Reactor Vessel Heights

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

L-2008-236 Page 11 of 42 Item Parameter -Description Units Value Comments No.

2.

Volume versus height for the reactor vessel with S eT b e6S eT be6----

internals installed

13.

Reactor Coolant Pump Rated Conditions

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

295 ft)

2.

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

91,000 & 87,500 gpm)

3.

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

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

4.

Speed rpm 900 Synchronous speed

5. Density The value is the average of the four Ibm/ ft3 47.5 pump-specific values (47.3, 47.4, 46.9 and 48.4 Ibm/ ft3)

6.

Homologous pump curves (four quadrant)

N/A See Table 7

7.

Pump inertia and friction (coefficients of polynomial Uncertainty value-of+ 1% may be in pump speed) lbm-ft2 102,000 applied to pump inertia in the analysis to gain operating margin.

ft-lbf 2735

- Constant for friction and windage torque.

8.

Coolant primary system fluid volume within pump ft3 112

9.

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

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

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

20 (max)

12. Coastdown characteristics N/A Figure 2

L-2008-236 Pane 12 of 42 Item Parameter -Description Units Value Comments No.

13. Pump trip setpoints N/A Overcurrent Overload Trip

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

14.

Core Cooling System

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

2.

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

3.

SIT initial pressure and liquid volume

°(500 to 650 +

psia

15)

TS ranges for SIT pressure and liquid Wft3 (1420 to 1556 +

volume.

32)

4.

CST minimum capacity gal 276,200

5.

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

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

J EL

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

2.

SG pressure (including bypass and ADV)

Later Later Later

3. Pressurizer heaters and sprays Later Later Later

4.

Pressurizer level Later Later Later

5.

Auxiliary feedwater Later Later Later 6

(VVC('.

(char ino and lptdnxwnl I ntpr I ntpr T atpr 15.b Control Systems EPU condition operation of the primary and secondary control systems for:

L-2008-236 Page 13 of 42 Item Parameter -Description Units Value Comments No.

7.

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

8. SG pressure (including bypass and ADV)

Later Later Later

9.

Pressurizer heaters and sprays Later Later Later

10. Pressurizer level Later Later Later 1 1. Auxiliary feedwater Later Later Later

12. CVCS (charging and letdown)

Later Late r Later

16.

Reactor Vessel Upper Head

1.

Uperhea flid empeatue a nomalAssume to be the same as the core o.Uperatn condfuidtempeats r

OtnraF Later outlet temperature since the Rx vessel opertin conitinsdoes not have upper head inj~ection.-

17.

Essential Valve Characteristics Number of valves, full open flow area, forward/1 reverse flow coefficients (CV's), open/close rate, minimum flow at rated conditions, logic for opening ****

an closing the valves for:

SeTl1

1. Pressurizer PORVs See Table 12----

2.

Pressurizer safety valves See Table 12

3. Main steam safety valves See Table 12

4. Atmospheric dump valves See Table 12

5. TCVs (turbine control valves)

See Table 12

6. Turbine bypass valves See Table 12

7. TSVs, (turbine stop valves)

See Table 12

8. MFIVs See Table 12

9.

MSIVs See Table 12

L-2008-236 Page 14 of 42 Item Parameter -Description Units Value Comments No.

18.

to Reactor Core Parameters 20.

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

2.

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

3.

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

4. Moderator temperature coefficient Later Later Later

5. Typical top peaked axial power profile Later Later Later

6.

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

7.

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

8.

Gap conductance Later Later Later

9.

Linear heat rate Later Later Later

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

21.

Operator Actions During LOCA

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

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

2.

HPSI throttling criteria If HPSI pumps are operating, See Comments and ALL of the following conditions None Section.

are satisfied:

__RCS subcooling is greater than or

L-2008-236 Page 15 of 42 Item Parameter -Description Units Value Comments No.I equal to minimum subcooling

- Pressurizer level is at least 30%

and NOT lowering,

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

3.

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

Most recent COLR provided to NRC

22.

Core Operating Limits Report See Comment See Comment 207 EPl LR2to7b1provded later 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, etc.):

1. Density Later Later Later

2.

Specific heat Later Later Later

3. Thermal conductivity Later Later Later

4.

Ernissivity versus temperature Later Later Later

L-2008-236 Page 16 of 42 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 +

55 +

CL 0

5.

> 5O

-1 I.(U

-J w

> 45

-- I N

40 w

t0l

-I-

-I-35 +

(538.2, 33.1) 30 25 520.0 530.0 540.0 550.0 560.0 570.0 580.0 TAVE (F) 590.0 Pressurizer Volume at 63.0% Span is 914 Cu. Ft.

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

L-2008-236 Page 17 of 42 Figure 2 - RCP IITlrl L

Note: Curve represents current analyses.

L-2008-236 Page 18 of 42 Figure 3

L-2008-236 Page 19 of 42 Figure 4 E -8ý,

L-2008-236 Page 20 of 42 Table 1 (Later)

L-2008-236 Page 21 of 42 Table 2 (Later)

L-2008-236 Page 22 of 42 Table 3 Unit 2 Piping Isometric Drawings by P&ID Flow Diagram Component/Isometric Drawing Reactor Vessel 2998-G-078, Sheet 110, Rev. 08

/ 2998-769, Rev. 2 Primary Loop Piping (RCS) 2998-G-078, Sheet 110, Rev. 08 2998-2662, Rev. 4 2998-2132, Rev. 6 2998-3793, Rev. 1 2998-1887, Rev. 3 2998-1886, Rev. 6 Reactor Coolant Pumps 2998-G-078, Sheet Il1A, Rev. 11 2998-455, Rev. 6 2998-G-078, Sheet 111B, Rev. 10 2998-457, Rev. 8 2998-G-078, Sheet 11 IC, Rev. 13 2998-G-078, Sheet 1IID, Rev. 10 Steam Generators 2998-G-078, Sheet 110, Rev. 8 2998-21342 Rev 0 (Later) 2998-G-079, Sheet 1, Rev. 41 2998-G-080, Sheet 2A, Rev. 43 Pressurizer/Surge Line/Spray Lines/Relief Lines 2998-G-078, Sheet 109, Rev. 18 2998-506, Rev 4 2998-G-078, Sheet 108, Rev. 5 2998-G-125, Sheet RC-AB-1, Rev 13 2998-G-125, Sheet RC-AB-2, Rev 11 2998-2048, Rev 5 Main Steam Lines Out to the Turbine Stop Valves 2998-G-079, Sheet 1, Rev. 41 2998-G-125, Sheet MS-L-1, Rev. 22 2998-G-079, Sheet 2, Rev. 35 2998-G-125, Sheet MS-L-2, Rev. 22 2998-G-125, Sheet MS-L-3, Rev. 10 2998-G-125, Sheet MS-L-4, Rev. 16 2998-G-125, Sheet MS-L-13, Rev. 11

__2998-G-125, Sheet MS-L-14, Rev. 16 Main Feedwater Lines from the Isolation Valves to the Steam Generator Inlet 2998-G-080, Sheet 2A, Rev. 43 J 2998-G-125, Sheet BF-M-6, Rev. 17 Auxiliary Feedwater Lines 2998-G-080, Sheet 2B, Rev. 36 2998-G-125, Sheet BF-M-7, Rev. 18 2998-G-125, Sheet BF-M-8, Rev. 20 2998-G-125, Sheet BF-M-9, Rev. 16 Safety Injection 2998-G-078, Sheet 130A, Rev. 19 2998-G-078, Sheet 130B, Rev. 28 2998-G-078, Sheet 131, Rev. 20 2998-G-078, Sheet 132, Rev. 09 2998-G-078, Sheet 110, Rev. 08 2998-G-125, Sheet SI-N-4, Rev. 20 2998-G-125, Sheet SI-N-5, Rev. 19 2998-G-125, Sheet SI-N-6, Rev. 18 2998-G-125, Sheet S1-N-7, Rev. 15 2998-G-125, Sheet SI-N-8, Rev. 18

L-2008-236 Page 23 of 42

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-078, Sheet 120, Rev. 17 2998-G-078, Sheet 121A, Rev. 31 2998-G-078, Sheet 122, Rev. 25 2998-G-125, Sheet CH-G-1, Rev. 21 2998-G-125, Sheet CH-G-2, Rev. 19 2998-G-125, Sheet CH-G-3, Rev. 16 2998-G-125, Sheet CH-G-4, Rev. 21 2998-G-125, Sheet CH-G-10, Rev. 12 2998-G-125, Sheet CH-G-14, Rev. 11 2998-G-125, Sheet CH-G-15, Rev. 15 2998-G-125, Sheet CH-G-16, Rev. 06 2998-G-125, Sheet CH-G-17, Rev. 13 2998-C-124, Sheet CH-1, Rev. 11 2998-C-124, Sheet CH-3, Rev. 12 2998-C-124, Sheet CH-4, Rev. 09 2998-C-124, Sheet CH-6, Rev. 8 2998-C-124, Sheet CH-33, Rev. 7 2998-C-124, Sheet CH-72, Rev. 15 2998-C-124, Sheet CH-75, Rev. 14 2998-C-124, Sheet CH-78, Rev. 12 2998-C-124, Sheet CH-103, Rev. 9 2998-C-124, Sheet CH-104, Rev. 8 2998-C-124, Sheet CH-105, Rev. 6 2998-C-124, Sheet CH-106, Rev. 13 2998-C-124, Sheet CH-108, Rev. 7 2998-C-124, Sheet CH-109, Rev. 17 2998-C-124, Sheet CH-1 10, Rev. 14 2998-C-124, Sheet CH-I11, 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-2008-236 Page 24 of 42 Table 4 Spacer Grid Locations Grid #

Distance (in) 1 5.175 2

22.375 3

38.188 4

54.000 5

69.812 6

85.625 7

101.438 8

117.250 9

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

L-2008-236 Page 25 of 42 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 (Nornal)

+/- 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)

RPS S/G Level Lo 20.5%

> 20.5%

+ 5% (Normal)

+/- 5% (Normal)

+ 14% (Accident)

RPS RCS Low Flow

> 95.4% Design 3.5%

3.5% (Normal)

Flow 7.5% (Accident)

SIAS/CIS Cont. Press Hi 3.41 psig

< 3.5 psig

+ 1.65 psi

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

< 5.4 psig

+/- 1.65 psi

+ 1.65 psi SIAS PZR Press Lo 1740 psia"

> 1736 psia

+/- 45 psi (Normal)

+/- 90 psi (Accident)

+ 90 psi (Accident)

MSIS S/G Press Lo 600 psia

> 600 psia

+ 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)

+ 14% (Accident)

AFAS S/G Press DP Hi 270 psid

< 275 psid Not specified

+ 60 psi (Normal)

+/- 115 psi (Accident)

AFAS FW Press DP Hi 142.5 psid

< 150.0 psid Not specified

< 245 psid (setpoint)

EPU setpoint requirement based on

+/- 85 psi (Nornal) 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 I tolerance)

+ 3% (Bank 1 tolerance) 1040 psia (nominal)

+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-2008-236 Page 26 of 42 Table 6 1.

-2:0

L-2008-236 Page 27 of 42 Table 6 - Continuation

L-2008-236 Page 28 of 42 Table 7 Table 2 - Reactor Coolant Pump Homologous Curves VALPHA HAN HVN BAN BVN HAD HVD BAD BVD 0.0000 1.5800

-1.4200 0.7700

-1.4500 1.5800 1.2200 0.7700 1.3150 0.1000 1.5000

-1.2150 0.8020

-1.1120 1.6600 1.2850 0.8100 1.3800 0.2000 1.4200

-1.0820 0.8450

-0.8720 1.7600 1.3450 0.8800 1.4500 0.3000 1.3700

-0.9120 0.8660

-0.6480 1.8700 1.4400 0.9800 1.5100 0.4000 1.3300

-0.7280 0.8850

-0.4420 2.0000 1.5500 1.0900 1.5800 0.5000 1.2950

-0.4940 0.9100

-0.2700 2.1300 1.7200 1.2350 1.6400 0.6000 1.2700 0.0000 0.9300 0.2600 2.3000 1.9300 1.3900 1.7200 0.7000 1.2400 0.2080 0.9530 0.4300 2.4700 2.1800 1.5800 1.8300 0.8000 1.1820 0.4350 0.9730 0.6130 2.7000 2.4900 1.7850 1.9600 0.9000 1.1050 0.7080 0.9890 0.8000 2.9300 2.8100 2.0400 2.1200 1.0000 1.0000 1.0000 1.0000 1.0000 3.1500 3.1500 2.2900 2.2900 VALPHA HAT HVT BAT BVT HAR HVR BAR BVR 0.0000 0.4330 1.2200

-1.4400 1.3150 0.4330

-1.4200

-1.4400

-1.4500 0.1000 0.4740 1.1820

-0.9200 1.2450 0.3430

-1.7150

-1.6600

-1.8500 0.2000 0.5020 1.1400

-0.6300 1.1800 0.0112

-1.9600

-1.9100

-2.2000 0.3000 0.5120 1.0850

-0.4200 1.1100

-0.2460

-2.1500

-2.1900

-2.5200 0.4000 0.5240 1.0450

-0.2500 1.0420

-0.5130

-2.3400

-2.4900

-2.8500 0.5000 0.5460 1.0000

-0.1000 0.9750

-0.8300

-2.5200

-2.8300

-3.1500 0.6000 0.5830 0.9500 0.0200 0.9050

-1.0350

-2.6900

-3.2400

-3.4900 0.7000 0.6410 0.9000 0.1300 0.8170

-1.6000

-2.8100

-3.6000

-3.8400 0.8000 0.7120 0.8700 0.2510 0.7280

-2.0500

-2.9300

-4.0500

-4.2300 0.9000 0.8000 0.8650 0.3900 0.6280

-2.5500

-3.0100

-4.5400

-4.6100 1.0000 0.9080 0.9080 0.5620 0.5620

-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-2008-236 Page 29 of 42 Table 8 (Sheet 1 of 2)

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

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

A2 (gpm)

(psia)

A2 (gpm) 1408 0

1165 0

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

2050 0

1620

L-2008-236 Page 30 of 42 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)

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-2008-236 Page 31 of 42 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-2008-236 Page 32 of 42 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 BI 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-2008-236 Page 33 of 42 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)

B1 or B2 (psia)

BI 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-2008-236 Page 34 of 42 Table 11 (Sheet 1 of 2)

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

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

A2 (gpm)

(psia)

A2 (gpm) 1408 0

1198 0

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

2000 0

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

1453 0

1548

L-2008-236 Page 35 of 42 Table 11 (Sheet 2 of 2)

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

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

B2 (gpm)

(psia)

B2 (gpm) 1408 0

1198 0

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

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

151

L-2008-236 Page 36 of 42 Table 12 Component Data Required Component Flow Diagram Component Information Pressurizer PORVs V1474 2998-G-078 Sheet 108 Rev. 5 2998-18810 Rev. 3 V 1475 Pressurizer Safety Valves V 1200 2998-G-078 Sheet 109 R18 2998-19690 Rev. I V1201 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 FCV-08-641 2998-G-079 Sheet 2, Rev.35 2998-2184 Rev. 10 2998-31, Rev 17

L-2008-236 Page 37 of 42 FCV-08-643 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 I

HCV-09-2B_

Main Steam Isolation Valves HCV-08-1A T 2998-G-079 Sheet 1, Rev. 41 2998-1011 Rev. 3 Sheet 1/9 HCV-08-1B 2998-1012 Rev. 3 Sheet 2/9 Miscellaneous Components V09107 2998-G-080 Sheet 2B Rev.36 2998-20110 Rev. 1 V09108 2998-741 Rev. 3 SE-09-2 2998-13008 Rev. 3 2998-13006 Rev. 1 2998-13009 Rev. 2 MV-09-9 2998-19745 Rev. 2 2998-1872 Rev. 6 2998-5616 Rev. 0 V09119 2998-3033 Rev. 4 V09120 2998-742 Rev. 2 V09123 2998-20110 Rev. 1 V09124 2998-741 Rev. 3 SE-09-3 2998-13008 Rev. 3 2998-13006 Rev. 1 2998-13009 Rev. 2, MV-09-10 2998-19745 Rev. 2 2998-1872 Rev. 6 2998-5617 Rev. 0 V09135 2998-3033 Rev. 4 V09136 2998-742 Rev. 2 V09139 2998-752 Rev. 5 V09140 2998-751 Rev. 2 SE-09-4 2998-13007 Rev. 1 2998-13008 Rev.3 2998-13009 Rev. 2 MV-09-11 2998-19745 Rev. 2 2998-1871 Rev. 7 2998-5617 Rev. 0 V09151 2998-3033 Rev. 4 V09152 2998-742 Rev. 2 SE-09-5 2998-13007 Rev. ]

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

L-2008-236 Page 38 of 42 V3225 V3624 V3258 V3227 V3215 V3614 V3259 V3217 V3245 V3644 V3261 V3247 V3235 V3634 V3260 V3237 FE-3312 HCV-3615 V3114 V3805 FE-3311 V3113 HCV-3616 HCV-3617 FE-3322 HCV-3625 V3124 HCV-3626 FE-3321 V3766 HCV-3627 FE-3332 HCV-3635 V3134 FE-3331 V3133 HCV-3636 HCV-3637 FE-3342 V3144 FE-3341 2998-G-078 Sheet 132 Rev. 9 2998-G-078 Sheet 131 Rev. 20 2998-19174 Rev. 2 2998-4353 Rev. 5 2998-784 Rev. 6 2998-655 Rev. 1 2998-658 Rev. 1 2998-19174 Rev. 2 2998-4353 Rev. 5 2998-784 Rev. 6 2998-655 Rev. 6 2998-658 Rev. 1 2998-4353 Rev. 5 2998-19174 Rev. 2 2998-784 Rev. 6 2998-655 Rev. 1 2998-658 Rev. 1 2998-19174 Rev. 2 2998-4353 Rev 5 2998-784 Rev. 6 2998-655 Rev. 1 2998-658 Rev. 1 2998-1219 Rev. 9 2998-655 Rev. 1 2998-2076 Rev. 19 2998-19800 Rev. 0 2998-20356 Rev. 0 2998-20355 Rev. 0 2998-20356 Rev. 0 2998-20355 Rev. 0 2998-1219 Rev. 9 2998-655 Rev. 1 2998-1218 Rev. 9 8770-14084 Rev. 1 8770-14099 Rev. 1 2998-1218 Rev. 9 2998-1219 Rev. 9 2998-655 Rev. l 2998-1530 Rev. 5 2998-1218 Rev. 9 2998-1218 Rev. 9 2998-655 Rev. I

L-2008-236 Page 39 of 42 V3143 HCV-3646 HCV-3647 V3106 V3206 FCV-3306 FE-3306 V3107 V3207 FCV-3301 FE-3301 SO-03-19 V3427 V3656 SO-03-20 V3414 V3654 V2674 V2501 V2118 V2322 SS-02-1A Suction Stabilizer for CHG PP 2A Pulsation Damper for CHG PP 2A V2169 V2336 V2319.

SS-02-IB Suction Stabilizer for CHG PP 2B Pulsation Damper CHG PP 2B V2168 V2464 V2316 SS-02-IC Suction Stabilizer for CHG PP 2C 2998-G-078 Sheet 130B Rev. 28 2998-G-078 Sheet 130A Rev. 19 2998-G-078 Sheet 121A Rev. 31 2998-G-078 Sheet 122 Rev. 25 2998-20097 Rev. 0 2998-1218 Rev. 9 2998-1218 Rev. 9 2998-657 Rev. 2 2998-1024 Rev. 3 2998-4815 Rev. 7 2998-4816 Rev. 6 2998-657 Rev. 2 2998-1024 Rev. 3 2998-4815 Rev. 7 2998-4816 rev. 6 2998-679 Rev. 7 2998-781 Rev.3 2998-679 Rev. 7 2998-780 Rev.3 2998-16238 Rev. 0 2998-3386 Rev. 4 2998-1036 Rev. 1 2998-1033 Rev. 0 2998-7437 Rev. 3 2998-9068 Rev. 5 2998-9067 Rev. 4 2998-9070 Rev. 2 2998-9069 Rev. 2 8770-14084 Rev. 1 8770-14099 Rev. 1 8770-14345 Rev. 1 2998-1033 Rev. 0 2998-7437 Rev. 3 2998-9068 Rev. 5 2998-9067 Rev. 4 2998-9070 Rev. 2 2998-9069 Rev. 2 8770-14084 Rev. 1 8770-14099 Rev. 1 8770-12770 Rev. 1 2998-17048 Rev. 0 2998-1033 Rev. 0 2998-7437 Rev. 3 2998-9068 Rev. 5 2998-9067 Rev. 4

L-2008-236 Page 40 of 42 Pulsation Damper for CHG PP 2C V2167 V2339 FE-2212 V2429 V2523 V2462 V2535 V2598 V2485 V2433 SE-02-2 V2484 V2432 SE-02-1 V2593 V2515 V2516 V2522 V2341 V2342 (Letdown Heat Exchanger)

LTDN HT EXCH V2347 PCV-220.1Q V2349 FE-2202 V2358 (Purification Filter)

Purif Filter 2A 2998-9070 Rev. 2 2998-9069 Rev. 2 8770-14084 Rev. 1 8770-14099 Rev. 1 2998-1031 Rev. 5 2998-560 Rev. 2 2998-2786 Rev. 5 8770-14084 Rev. 1 8770-14099 Rev. 1 2998-560 Rev. 2 2998-15232 Rev. 3 2998-3487 Rev. 2 2998-1749 Rev. 3 2998-18973 Rev. 0 2998-18974 Rev. 0 2998-19677 Rev. 0 2998-19678 Rev. 0 2998-3487 Rev. 2 2998-1749 Rev. 3 2998-18973 Rev. 0 2998-18974 Rev. 0 2998-19677 Rev. 0 2998-19678 Rev. 0 2998-1009 Rev. 2 2998-548 Rev. 14 2998-548 Rev. 14 2998-2785 Rev. 5 2998-560 Rev. 2 2998-17024 Rev. 0 2998-560 Rev. 2 2998-17023 Rev. 0 2998-1611 Rev. 1 2998-557 Rev. 3 2998-17023 Rev. 0 2998-2586 Rev. 6 2998-4013 Rev. 0 2998-17023 Rev. 0 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-19775 Rev. 0 2998-6065 Rev. 3 2998-16332 Rev. 1 2998-5498 Rev. 4 2998-G-078 Sheet 120 Rev. 17

L-2008-236 Page 41 of 42 V2360 V2520 V2359 V2370 (Purification Ion Exchanger)

Purif IX 2A V2378 V2382 V2395 (Letdown Strainer)

S2900 V2415

.V2418 V2452 (Purification Filter)

Purif Filter 2B FE-8011 FE-8021 V1442 V1249 PCV-1IOOF V 1444 V1477 V 1479 V1476 V1478 V 1443 PCV-1100E V 1248 V 1441 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-2584 Rev. 6 2998-590 Rev. 5 2998-17042 Rev. 1 2998-1029 Rev. 2 2998-3642 Rev. 2 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-17025 Rev. 0 2998-1037 Rev. 1 2998-5064 Rev. 1 2998-17025 Rev. 0 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-1037 Rev. 1 2998-19775 Rev. 0 2998-5498 Rev. 4 2998-6065 Rev. 3 2998-16332 Rev. 1 2998-1420 Rev.6 2998-1421 Rev. 4 2998-2646 Rev. 1 2998-3066 Rev. 5 2998-17056 Rev. 0 2998-187 Rev. 3 2998-546 Rev. 13 2998-3066 Rev. 5 2998-17057 Rev. 0 2998-13278 Rev. 3 2998-13277 Rev. 0 2998-13278 Rev. 3 2998-13277 Rev. 0 2998-3066 Rev. 5 2998-17057 Rev. 0 2998-546 Rev. 13 2998-187 Rev. 3 2998-3066 Rev. 5 2998-17055 Rev. 0 2998-G-079 Sheet 1, Rev. 41 2998-G-078 Sheet 109 Rev. 18 2998-G-078 Sheet 108 Rev. 5 2998-G-078 Sheet 109 Rev. 18

L-2008-236 Page 42 of 42 FE-01-2 FE-01-1 FE-09-2A FE-09-2B FE-09-2C MV-08-14 MV-08-15 MV-08-16 MV-08-17 V08359 V08360 V09294 V09252 2998-G-078 Sheet 108 Rev. 5 2998-G-080 Sheet 2B Rev.36 2998-G-079 Sheet 1 Rev. 41 2998-G-079 Sheet 2 Rev. 35 2998-G-080 Sheet 2A Rev 43 2998-13912 Rev. 1 2998-13912 Rev. 1 2998-2595 Rev. 2 2998-2595 Rev. 2 2998-2595 Rev. 2 2998-10622 Rev. 5 2998-10622 Rev. 5 2998-10621 Rev. 6 2998-10621 Rev. 6 2998-3012 Rev. 8 2998-3012 Rev. 8 2998-2143 Rev. 5 2998-2143 Rev. 5

L-2008-236, Extended Power Uprate, Data for NRC Confirmatory EPU Analyses

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