L-2008-262, Extended Power Uprate Data for NRC Confirmatory EPU Analyses
| ML083570214 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, Susquehanna  |
| Issue date: | 12/18/2008 |
| From: | Katzman E Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2008-262 | |
| Download: ML083570214 (91) | |
Text
0 FPL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 December 18, 2008 L-2008-262 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 provides additional 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, l 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
L-2008-262 Attachment I Page 1 of 43 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 h
la For rated power conditions (Current)
- 1. Primary and Secondary Flow rates:*',,;kNN i*
- 1. 1. Core flow
"!Unc: : 14,945 gpm and gpm 410,922 Ret. 4, Item 1.6*.29 min flow is 365,000 gpm 1.2. Main coolant pumps 95,000 (1A1) gpm 96,000 (1B1)
Ref. 8, Table 2 RCP Pump Test Data 95,000 (1 B1) 94,000 (1B2) 1.3. Steam flow lbm/s See Item la.7.1 1.4. Feedwater flow Ibm/hr See Item I a.7.1---------
1.5 SG recirculation ratio/boiler section flow Power-Power
%Circ Ratio 25 15.3 50 8.7 75 5.95 90 4.9 100 4.3 Reference 11, Figure 6.3
% CircRatio
- 2.
Primary and Secondary Pressures:
2.1. Pressurizer 2.2. Core inlet
L-2008-262 Attachment I Page 2 of 43 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 I psi pressure psia 2286 drop from RCP discharge to core inlet.
2.5. Steam generator dome Steam Generator Outlet from Benchmarked Heat psia 8631.5 Reference 11, Balance plus pressure drop pa 8eren 115 to Upstream Outlet Figure 10.5 NozzleAbove Primary Deck 2.6. Turbine control valve inlet psia See Item la.7.3 2.7. Detailed primary loop pressure drop From Cycle 15 data and distribution psi LaterTable 14 LaterRef. 29 0% SG tube pluging.Later
- 3.
Primary and Secondary Temperatures:
J!*
- t*,*~**,l*
'[**
~
- 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: +/- 3power.
3.3. Core outlet Current PI Process data.
3.4. Upper Head Assumed to be the same as
°F 599
-the core outlet temperature since the Rx vessel does not have upper head
L-2008-262 Item No.
Parameter -1
- 4.
Water levels in the pressurizer and steam generators.
4.1. Pressurizer
% Tap Span See Figure 1 Ref, 8, Attachment 1, Figure 3.
4.2. Steam Generators Reference SG elevations ft 35.0 Ref. 11 from bottom of support skirt base.
- 5. Leakage flows (Bypass):
% of vessel flw3.9 Ref.8, Item 10.
flow 5.1. Outlet nozzle clearances Ref 1, Table 4.4-3, percent 1.18 Ie~2 Item 2.
5.2. Downcomer to upper head Ref 1, Table 4.4-3, percent 0.17Itm1&6 Items 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 I a.5.5.1). This has not been quantified.
5.4. Upper head to upper plenum (guide pecn
/
This has not been structure holes) pret/Aquantified.
5.5.ba eCore bypass (guide tubes, barrel-I**
- i.,.
.i
- "}
5.5.1. Guide tubes Ref. 1, Table 4.4-3, t1.86 Item 5 (HVFR fuel assemblies not used).
5.5.2. Barrel-baffle percent 0.50 Ref 1, Table 4.4-3, Items 3 and 4.
- 6.
Steam generator recirculation ratio Power-
%CircRatio See Item Ia. 1.5
L-2008-262 Attachment I Page 4 of 43 Item Parameter -Description Units Value Reference Comments No.
- 7.
Heat balance information, such as:
- 7. 1. Feedwater and steam flows lbm/hr 11,851,050 Reference 9 Benchmnarked Heat 11,784,590 Balance 7.2. Feedwater temperature OF45Rfrne9Benchimarked Heat l b.
For EPU conditions.
gpF 410,922 Ref 4, Item 1.6.29 measurement. Unc:9 15,000 gpmn; TS Min flow is 375,000 gpm 1.2. Main coolant pumps 95,000 (BAl) gpm 96,000 (.A2)
Refr3,nAttach RCP Pump Test Data 94,000 (11B2) 1.3. Steam flow Ibm/s See Item lb.7.1 1.4. Feedwater flow Ibm/hr See Item lb.7.l 1.5. SG recirculation ratio/boiler section flow Power-Later Later Later
% CircRatio
- 2.
Primary and Secondary Pressures:
.7-2.1. Pressurizer fow 2225 to 2275 on gpsi 102Unc:4 Ref. 4, Item 1.6.3 1 2.2. Core inlet psia 2285 Assumed to remain similar
.5.SGeirculationratio/boersection-to currentconditions.
L-2008-262 Page 5 of 43 Item Parameter -Description Units Value Reference Comments No.
2.3. Core outlet psia 2250 Assumed to remain similar 2250 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 Later 2.6. Turbine control valve inlet psia See Item lb.7.3 2.7. Detailed primary loop pressure drop LaterTable 14 LaterRef 27 Assumes 10% SG tube distribution plugging.Later
- 3. Primary and Secondary Temperatures:
MIA I
i 3.1. Hot leg Ref. 28Ref. 4, Page Assumes 10% SG tube 17 of 79 states that plugging.Assume to be the OF 606.0 Later safety analysis will same as the core outlet determine.value temperature since the Rx during EPU vessel does not have upper analysis.
head injection.
3.2. Cold leg 551 Ref. 4, Page 17 of Corresponds to 100%
OF
+/-Power.
Tcold at 0% power is 532 0F.
3.3. Core outlet Safety analysis will Assumes 10% SG tube determine value plugging.mSafety analysis during EPU will determine value analysis.Ref. 28 during EPU analysis.
3.4. Upper Head OF 608.2 Later Ref. 28Safety analysis will determine value during EPU analysis.
Assumed to be the same as vessel outlet. Assume to be the same as the core outlet temperature since the Rx vessel does not have upper head iniection.
i 4. Water levels in the pressurizer and steam generators.
4.1. Pressurizer i
4.2. Steam Generators
L-2008-262 Attachment I Page 6 of 43 Item Parameter -Description Units Value Reference Comments No.
does not change for EPU.
- 5. Leakage flows (Bypass):
V 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.CEA hrods prcen N/
This has not been 5.3.CEA hrous pecentN/Aquantified.
5.4. Upper head to upper plenum (guide This has not been structure holes) pc N/A quantified.
5.5. Core bypass (guide tubes, barrel-!iN*
baffle)
EPU conditions.e and-nstrument(A) 5.5.1. Guide tubes percent 2.00 Ref 4, Sec. 1.6.
ude s
n NubnclaesCompany 5.5.2. Barrel-baffle percent 0.54 Ref. 4, Sec. 1.6.
IncludsCoeShru
- 6.
Steam generator recirculation ratio Pow er-S e It m Ib 1.5-
%CircRatio T. Heat balance information, such as:
II*
- 7. 1. Feedwater and steam flows lbm/hr 13,305,870 Reference I10Later Draft Heat BalanceWill be 13,239,440Later provided when finalized 7.2. Feedwater temperature OF 436.2Later Reference I10Later Draft Heat BalanceWill be provided when finalized 7.3. Turbine inlet pressure Draft Heat Balance, psia 802.5Later Reference I10Later Turbine Valve InletWill be provided when finalized
- 2.
Analysis Topical Reports See References provided
- 1. Topical Report on the licensing analysis beelower:
icbe orae of record for LOCA at rated power and SeSee Comlment See Comlment pwr EUcniin.Comment XN-NF-82-49(P)(A),
EPU cnditons.Rev.
1, "Exxon Nuclear Company
L-2008-262 Attachment I Pane 7 of 43 Item Parameter -Description Units Value Reference Comments No.
Evaluation Model Revised EXEM PWR Small Break Model",
- EMF-2328(P)(A),
"PWR Small Break LOCA Evaluation Model, S-RELAP5 Based",
- EMF-2087(P)(A),
"SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications".
- EMF-2514, Rev. 0, "St.
Lucie Unit 1 Large Break LOCA/ECCS Analysis," Dec. 2000.
For EPU, the SBLOCA Topical Report from above will be used. For LBLOCA, the EPU Topical Report is: EMF-2103(P)(A), Rev. 0, "Realistic Large Break LOCA Methodology for PWRs". Analysis results are in the UFSAR.
- 3.
Safety System Logic, Setpoints and Delay Times SCritical Safety Parameters List (also called "Groundrules document") for the last reload for:
- 1. ESFAS
L-2008-262 Attachment I Page 8 of 43 Item Parameter -Description Units Value Reference Comments No.
- 2.
RPS See Table 11 See Table 11 See Table 11 See Table 11
- 3. SGIS/MSIS See Table 11 See Table 11 See Table 11 See Table 11
- 4.
PORV See Table 11 See Table I 1 See Table 11 See Table 11
- 5.
SRV See Table 11 See Table 11 See Table I I See Table 11
- 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
- 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) 6.8 a) Inlet nozzle & 90 degree psi b) 21.5 Ref 1, Table 4.4-4
- turn, c) 7.1 b) Downcomer, lower plenum, support structure
L-2008-262 Attachment I Page 9 of 43 Item Parameter -Description Units Value Reference Comments No.
& 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 & L.b.5.5 flow l.b.5.5 above above
- 6. Nmberand ocaton o fue rod N/A176 per AssT.
Ref. 1, Table 4.2-10 Seeatigueon.
d o
- 6.
umeran lcaio o felros
/A38,192 totalloain
- 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 To confiry 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 plen See Table 6 including upper plenum or head to--SeTal6---------
downcomer, if available).
- 2.
Primary loop piping (hot leg, cold leg, See Table 6 pump suction).
- 3. Reactor coolant pumps.
See Table 6 at
- 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
L-2008-262 Page 10 of 43 Item Parameter -Description Units Value Reference Comments No.
valves, flow restrictors, etc.
- 7. Main feedwater lines from the isolation valves to the steam generator inlet.
- 8.
Auxiliary feedwater lines and feedwater See Table 6 pump type, configuration and capacity.
- 9.
Safety injection equipment including SITs, high and low pressure injection systems and See Table 6 connecting piping.
- 10. Charging and letdown system (CVCS).
See Table 6
- 11. Residual heat removal system.
See Item 6.9 for LPSI See Comment System. LPSI and RHR are the same system.
- 7.
Reactor Vessel Internals Dy( wWeight and surface area of reactwei**g vessel internal structures:
- 1. Core support barrel Includes upper, center, and lower portions of the core 90,000103,500 /
support barrel; upper and Later 1046 lower flange; inner and Lbs sq. ft.
Inside outer nozzle areas.et 1106 outside value (Dry weight is 103,000 lbs)
- 2.
Core shroud Wet value 31,0004 900(Dry weight is 35,000 31,00034,t.
9 00 /n'd Ref. 30Ref. 4, lbs)Includes vertical and 85otieLtrTable 10 horizontal surfaces of the core shroud. Weight includes Tie Rods.
- 3. Upper andL lower core support. plates Upper: 18,463 Includes top and bottom Lower:
Ref. 30Ref. 4, surfaces; surface areas 12,4677,900 Tables 10 and 7.
inside the holes of the
/ 243 Later plate.---
L-2008-262 Attachment I Page I Iof 43 Item Parameter -Description Units Value Reference Comments No.
- 4.
Fuel alignment plate (Upper Core Plate)
Includes top and bottom NA 8,900 / Later Ref. 30Refs. 13 &
surfaces; surface areas 238 14 inside the holes of the plate.-
- 5. Upper guide structure Includes CEA shrouds with extensions; total UGS plate, beam, &
cylinder areas; total fuel Lbs / sq. ft.
82,00094,400 /
Ref. 30Ref. 15 alignment plate area Later 6040 Ref. 4, Table 10 (Neglects guide tubes).Includes expansion compensating ring, fuel alignment plate, upper core plate and CEA shroud.
- 6. Core support assembly Wet value (Dry weight is 48,000 lbs)
Lbs / sq. ft.
4247,000 800 /
Ref 30Ref 5 Includes vertical webs; Later 1371 flanges; cylinder; columns core support plate (Item 3 above); bottom plate.
- 7. Flow skirt Includes top and bottom Lbs / sq. ft.
2,5643,600 / Later Ref, 30Ref. 4, surfaces; surface areas 292 Table 6 inside the holes of the plate.---
- 8.
Control element assembly (CEA) shroud 44,41841,300 /
Includes single and double Lbs / sq. ft.
1980 Inside Ref, 30Ref. 4, shrouds.
2167 outside Table 10 Later
- 9.
Shroud extensions 3,000/
Includes single and double 386 Inside Icue igeaddul Lbs / sq. ft.
476 outside Ref 30Later shrouds.
otsder Later Later Lbs20.60
/ Later Appendix ALater Later
- 10. Grid assemblies Lbs / sq. ft.
71.2892 per Assy
L-2008-262 Attachment I Page 12 of 43 Item Parameter -Description Units Value Reference Comments No.
- 8.
Steam Generator Internals
- 1. Weight of steam generator ybside) ft 75 R
tube sheet yand.
surface area of tube sheet w oaer I
8 primary side fluid.
- 1. 1. Weight of Tube Sheet Includes base metal
- 3.
AitT9.4 (Ref, 3, Items B 1.348 (93,239 bm) and cladding lb 43635 and 61 (1095 lb.).
1.2. Area of Tube Sheet (Primary Side) ft2 751 Ref. 3, Itemn B 1.42 Area for tube sheet only.
- 2.
Weight and surface area of steam generator tuesN/
823Re.
, ttc 1
2.1. Weight of SG wrapper Ref. 4, Item 1. 12.3I5, Assume height of wrapper 5bm 25,955 36, and 37. Also, is 21.3 ft and material Ref. 21 density is 0.284 lbm/in73.
2.2. Surface area of SG wrapper ft2 Inner: 842 Ref, 4, Item 1. 12.3 5, suehihtorpe Outer: 850 and 37. Also, Ref.
Asmis 21.3 ft.hegto rpe 21
- 9.
Steam Generator Fluid Volumes.
- 1. Inlet plenum Wt 222.026 Ref. 3, Item B1. 1 Including Manway
- 2.
Outlet plenum ft 3 222.665 Ref. 3, Item B 1. 6 Including Manway
- 3. Active tubes, Outlet Inactive Tubes, Inlet o 1129.04 (Active),
Ref. 3, L
tems B1.4, Inactive Tubes 36.635 (Outlet),
3, and 5.
36.635 (Inlet)
- 4.
Number of steam generator tubes N/A 8523 Ref. 3, Attach# #1, Item 43.
- 5. Length of shortest and longest tubes ft 50.786 Ref. 24 70.981
- 10.
Steam Generator Parameters L
- 1. Inventory and recirculation ratio versus loadLaeL trL trL tr (essential at rated power conditions).
Lae I
ae ae ae
L-2008-262 Attachment I Page 13 of 43 Item Parameter -Description Units Value Reference Comments No.
- 2.
SG flow areas, K-factors and flows Later Later Later Later
- 11.
MS Line Flow Restrictor
- 1. Restrictor flow area.
ft2 3.69 per SG IRef, 3, Section Outlet Nozzle Area 1
'2.35 per SG
] B6. 1.10 and 11.
Flow Venturi Area
- 12.
Steam Generator and Reactor Vessel Heights 1*
5 l
- 1. Volume versus height relationship for the steamn generators, with downcomer and ft' vs. ft See Table 3 Ref 11 boiler regions provided separately.
- 2.
Volume versus height for the reactor vessel ft S tRef.
1, Tables 4.4-with internals installed,.t v.f See Table 1 413, 4.4-4C, and Figure 4.4-21 J
- 13.
Reactor Coolant Pump Rated Conditions I1. Head ft 273.5 Ref. 4, Item 1.9.22
- 12.
Flow gpln 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 friction (coefficients of lbm-ft' 101,900 Ref 4, Item 1.9.23 polynomial in pump speed)
- 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 MW 14.6 MWt Ref 4, (nominal),
Item 1.15.13
L-2008-262 Attachment I Page 14 of 43 Item Parameter -Description Units Value Reference Comments No.
20 MWt (max)
- 13. Pump trip setpoints N/A Overcurrent Ref. 17 Overload Trip.
14, Pump time delays-and logic N/A N/A N/A N,o safety related RCP
~trips.
- 14.
Core Cooling System
Refs 3, Attach. 1, gpm 13 Tables 3 & 4 Ref. 4, Attach. #3
- 2.
SIT total volume ft3 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 Mode 1.
- 4. CST minimum capacity gal 110,000 Ref. 3, Attach. 1, Item 84
- 5. Charging pump flow versus pressure Reciprocal pump. Flow is 40 (nominal) to 49 Ref. 3, Attach. 1, per charging pump.
gpm (maximum)Nominal value does not include 4 gpm for RCP bleed off.
15.a Control Systems Rated power operation of the primary and Isecondary control systems for:
- 1.
SG water level instrumentation and controlLaeLtrLtrLtr (three-element)
- 2.
SG pressure (including bypass and ADV)
Later Later 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
L-2008-262 Page 15 of 43 Item Parameter -Description Units Value Reference Comments No.
- 6.
CVCS (charging and letdown)
Later Later Later Later 15.b Control Systems EPU condition operation of the primary and**'*lN,0
- ° i {*
secondary control systems for:
- 7. SG water level instrumentation and control See item Lcter (three-element)
- 8. SG pressure (including bypass and ADV)
Later Later Later Later
- 9. Pressurizer heaterys Later Later Later Later
- 10. Pressurizer level Later Later Later Later 1 1. Auxiliary feedwater L aiter Later Later Later
- 12. CVCS (charging and letdown)
Later Later Later Later
- 16.
Reactor Vessel Upper Head S
a Assume to be the same as
- 1. Upper head fluid temperature at normal See item m.b.3.4 core outlet temperature 5.F Later (turbisince the Rx vessel does not have upper head injection
- 17.
Essential Valve Characteristics!L Number of valves, full open flow area,
- ...*,1{
- i forward/ reverse flow coefficients (CV' s),
open/close rate, minimum flow at rated
,,1 thconditionS'avs, lorlgic for opening and closing 1
- I"
- I I1. 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---------
L-2008-262 Page 16 of 43 Item Parameter -Description Units Value Reference Comments No.
- 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 1
20 Reactor Core Parameters I
oto o netinvru ieatrseconds 3.1 Ref. 3, Item 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 B 12
- 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 Later 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.
Value of 6.96 assumes 100 15.0 (Max)
Ref 3, Items B7.10 SS rods. Without this 6.96 (Ave) and 11 assumption, the average is 1_
6.94 kW/ft.
- 10. Fuel average and centerline temperature as a function of burnup for the hot rod in the hot bundle.
Later Later Later Later
- 21.
Operator Actions During LOCA
L-2008-262 Page 17 of 43 Item Parameter -Description Units Value Reference Comments No.
- 1. Reactor coolant pump trips (conditions to Accident analysis assumes trip pumps -
automatic or manual)
LOOP concurrent with Pumps
- RLOCA, and pumps are not None automatically trip 15.4.1.
loaded onto EDGs or on LOOP manually operated. Same assumption for EPU analysis.
- 2.
HPSI throttling criteria None See Comment Ref. 18 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 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
L-2008-262 Attachment I Page 18 of 43 Item Parameter -Description Units Value Reference Comments No.
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 Sletter L-20072008-066244,
- 22.
Core Operating Limits Report Comment See Comment See Comment dated 0411-0527-20087.
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-2008-262 Page 19 of 43 Figure 1 PRESSURIZER LEVEL PROGRAM 100.0 80.0 CL a-(U
-jx Cw 60.0 40.0 20.0 0.0 +-
506 522 538 554 570 586 VESSEL AVERAGE TEMPERATURE, TAVE (F) 602 Figure 2 - RCP Coastdown on Total Loss of Flow
t0 o ~
uJ -
L-2008-262 Page 21 of 43 Figure 4 - Location of Fuel Assemblies in the Core
L-2008-262 Paue 22 of 43 St*
L-2008-262 Page 23 of 43 Table 1 Volume vs. Height for the Reactor Vessel with Internals Installed.
Region Elevation Volume vs. Height Volume (f)
( ft3 per ft)
(ft 3 )
UGS support plate to top of vessel 6.6 699 (Region V6)
FAP to UGS support plate (Region 10.6 114.2 1210 V5)
Core Region (Fuel Alignment Plate (FAP) to CSP) (Regions V2, V3 &
12.8 69.7 892 V4)
CSB to vessel annulus (Region V1, 29.7 35 1039.5 Annulus)
Bottom of vessel to Core Support Plate (CSP) (Region V1, Lower 10 950.5 Plenum)
Sources.: Ref. 1, Tables 4.4-4B, 4.4-4C and Figure 4.4-21.
L-2008-262 Page 24 of 43 Table 2 Component Data Required Component I Flow Diagram Component Information Pressurizer PORVs V1402 8770-G-078 Sheet 11OA, Rev 30 8770-9676 Rev 1 V1404 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 V1200 8770-G-078 Sheet 11OA, Rev 30 8770-13730, Rev I V1201 8770-13731, Rev 1 V1202 Main Steam Safety Valves V8201 8770-G-079, Sheet 1, Rev. 53 8770-993, Rev 4 V8202 8770-990, Rev 9 V8203 V8204 V8205 V8206 V8207 V8208 V8209 V8210 V8211 V8212 V8213 V8214 V8215 V8216 Atmospheric Dump Valves HCV-08-2A 8770-G-079, Sheet 1, Rev. 53 8770-12944, Rev 1 HCV-08-2B 8770-8971, Rev 1 Turbine Control Valves (Governor)
FCV-08-644 FCV-08-645 FCV-08-646 8770-G-079, Sheet 2, Rev. 45 8770-103, Rev 7 8770-115, Rev 11 8770-116, Rev 24
L-2008-262 Page 25 of 43 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 1
8770-14211, Rev 0 Main Steam Isolation Valves HCV-08-IA 8770-G-079, Sheet 1, Rev. 53 8770-9673, Rev 10 HCV-08-IB Main Steam Check Valves V08117 8770-G-079, Sheet 1, Rev. 53 8770-8950, Rev 4 V08148 8770-895 1, 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 IC)
PD (Pulsation Damper on CHG PP IC)
V02134 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. 1 8770-14099 Rev. 1 8770-14084 Rev. I
L-2008-262 Page 26 of 43 Component Flow Diagram Component Information V2336 FE-2212 V2429 V2430 MV-02-2 Regen HT EXCH (Regenerative Heat Exchanger)
V2319 SS-02-lB SS (Suction Stabilizer for Charging Pump IB)
CHG PP 1B (Charging Pump IB)
PD (Pulsation Damper on CHG PP IB)
V02133 V2337 V2316 SS-02-IA SS (Suction Stabilizer for Charging Pump 1A)
CHG PP lA (Charging Pump IA)
PD (Pulsation Damper on CHG PP IA)
V2339 V02132 V2338 SE-02-2 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 2998-19678 Rev. 0 2998-19677 Rev. 0 8770-14084 Rev. I V2433
L-2008-262 Attachment I Page 27 of 43 Component Flow Diagram Component Information SE-02-1 V2432 V2519 V2515 V2516 V2341 LCV-21 lOP 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-8011 FE-8021 V09252 V09294 AFWPP IA AFW PP 1B 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-G-080, Sheet 3, Rev 54 8770-G-080, Sheet 4, Rev. 41 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 8770-5736, Rev 4 8770-7139, Rev 3 8770-3044, Rev 3 8770-4409, Rev 0
L-2008-262 Page 28 of 43 Component I Flow Diagram Component Information AFW PP IC V09139 V09140 FE-09-2C MV-09-11 MV-09-12 V09151 V09157 V09152 V09158 V09123 V09107 V09108 V09124 FE-09-2A FE-09-2B MV-09-9 MV-09-10 V09119 V09135 V09120 V09136 V1403 V 1405 V 1406 V1407 PZR Quench Tank V 1252 V1253 PCV-1 100E PCV-I1OOF V1248 V 1249 V1250 V 1251 SO-03-13 SO-03-14 SO-03-15 V3427 V3405 V3414 V3654 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 8770-1251, Rev 2 2998-20110, Rev 1 8770-3775, Rev 6 8770-125 1, Rev 2 8770-1251, Rev 2 8770-3294, Rev 4 8770-3544, Rev 0 8770-6966, Rev 5 8770-6966, Rev 5 8770-3775, Rev 6 8770-3775, Rev 6 8770-3774, Rev 3 8770-1251, Rev 2 8770-1374, Rev 10 8770-1374, Rev 10 8770-1750, Rev 5 8770-1750, Rev 5 8770-898, Rev 3 8770-G-078 Sheet 1 A, Rev 30 8770-G-078 Sheet 130A, Rev 27 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, Rev 4 8770-16184, Rev 0 8770-1769, Rev 4 8770-1768, Rev 8 8770-1768, Rev 8 8770-1768, Rev 8.
8770-1377, Rev 6
L-2008-262 Page 29 of 43 Component [
Flow Diagram I
Component Information V3656 HCV-3616 HCV-3626 HCV-3636 HCV-3646 V3113 V3123 V3133 V3143 FE-3311 FE-3321 FE-3331 FE-334.1 HCV-3615 HCV-3625 HCV-3635 HCV-3645 V3114 V3124 V3134 V3144 FE-3312 FE-3322 FE-3332 FE-3342 HCV-3617 HCV-3627 HCV-3637 HCV-3647 V3106 V3107 V3206 V3207 FCV-3306 8770-G-078 Sheet 131A, Rev 27 8770-G-078 Sheet 130B, Rev 31 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 I 8770-2301, Rev 1 8770-2301, Rev 1 8770-2301, Rev 1 8770-1376, Rev 5 8770-1376, Rev 5 8770-1376, Rev 5 8770-1376, Rev 5 8770-3646, Rev 1 8770-3646, Rev 1 8770-9348, Rev 3 8770-9348, Rev 3 8770-861, Rev 2 8770-930, Rev 8 8770-2301, Rev I FE-3306
L-2008-262 Page 30 of 43 Table 3 Wl
L-2008-262 Page 31 of 43 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-2008-262 Attachmaent 1 Page 32 of 43 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
-3.245240
-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-2008-262 Page 33 of 43 Table 6 Unit 1 Piping Isometric Drawings by P&ID Flow Diagram Isometric/Component Drawing Reactor Vessel 8770-G-078, Sheet 1 OB, Rev. 26 8770-44, Rev 5 8770-8862, Rev 0 8770-8863, Rev 0 8770-8864, Rev 0 8770-8865, Rev 0 8770-8873, Rev 1 8770-8874, Rev 0 8770-8877, Rev 0 8770-15672, Rev 0 8770-15673, Rev 0 Primary Loop Piping (RCS) 8770-G-078, Sheet 1103B, 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 lIlA, Rev. 15 8770-15, Rev 8 8770-G-078, Sheet 111B, 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 1101B, 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-187, Rev I
L-2008-262 Page 34 of 43 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 ll0B, 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-I 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 8770-13-124 Sheet CH-2 Rev 2 8770-13-124 Sheet CH-3 Rev 3 8770-B--124 Sheet CH-4 Rev 4 8770-13-124 Sheet CH-37 Rev 2 8770-B-124 Sheet CH-43 Rev 5 8770-B-124 Sheet CH-63 Rev 7
L-2008-262 Page 35 of 43 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-1 Rev 6 8770-B-124 Sheet RC-2 Rev 7 8770-B-124 Sheet RC-3 Rev 6 8770-B-124 Sheet RC-4 Rev 5 8770-B-124 Sheet RC-6 Rev I
L-2008-262 Attachment I Page 36 of 43 Table 7. TEMPERATURE vs. DOPPLER REACTIVITY WORTH Current Analysis Value EPU Analysis Value FUEL TEMPERATURE DOPPLER REACTIVITY FUEL TEMPERATURE DOPPLER REACTIVITY
(*F)
(Ap)
(OF)
(Ap) 0.0 0.0*
250.0 0.0 400.0
-0.0037338 667.5
-0.0098574 808.1
-0.0128639 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/ft3)
REACTIVITY (Ap)
DENSITY (Ibm/ftf)
-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
.xO10 6
Note:
Reactivity corresponding to the most positive MTC @ HFP, BOC Table 9. RCS TEMPERATURE vs. MODERATOR REACTIVITY
L-2008-262 Page 37 of 43 Current Analysis Value EPU Analysis Value RCS MODERATOR RCS MODERATOR TEMPERATURE ('F)
REACTIVITY (Ap)
TEMPERATURE (°F)
REACTIVITY (Ap) 68.0 0.06345*
300.0 0.06345 No changes from No changes from 450.0 0.03959 current analysis.
current analysis.
532.0 0.01627 572.0**
0.0000"*
Notes:
Assumed/extrapolated to be the same as the next value.
Assumed to the nominal temperature at which the MTC would be equal to 0.0.
Table 10. AXIAL HEIGHT vs. AXIAL POWER SHAPE Current Analysis Value EPU Analysis Value (WEC)
(FPL)
AXIAL HEIGHT Axial Power Shape AXIAL HEIGHT Axial Power Shape
____ t____......______(*)(t).
2.2783 0.38000 2.278 0.81301 4.5566 0.710 4.556 0.92260 6.8349 1.370 6.834 1.00900 9.1132 1.635 9.112 1.21700 11.3917 1.020 11.390 1.04567 Notes:
FPL can not confirm the current values provided by Westinghouse for the Axial Power Shape data. FPL has provided values for the EPU from the current LOCA Containment Re-Analysis.
Axial height from the bottom of core.
L-2008-262 Page 38 of 43 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 > 1 1 F 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)
> 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 > 111 F but < 2000F.
RAS RWT Level Lo 48 inches 48 inches
+ 6 inches
+ 6 inches AFAS S/G Level Lo 19.5%
> 19.0%
+ 3% (Normal)
+/- 5% (Normal)
Current cycle safety analysis parameter document
+ 14% (Accident)
+ 14% (Accident) includes a target analysis value of +/- 5% (Normal)
AFAS S/G Press DP Hi 270 psid
< 275 psid Not specified
+/- 64 psi (Normal)
Worst Normal is defined as Containmient
+/- 160 psi (Worst Normal)
Temperature > 11 1F but < 2000F.
AFAS FW Press DP Hi 142.5 psid
< 150.0 psid Not specified
< 245 psid (setpoint)
AFAS logic time delay 235 sec 170 sec 170 sec (minimum act. time)
PORV Open Pressure N/A 2400 psia (nominal) 2400 psia (nominal)
For non-LTOP conditions, PORVs operate on RPS (setpoint)
PZR Press Hi Main Steam Safety RV N/A 1000 psia (nominal)
+ 1%, - 3% (tolerance) 3% (tolerance)
Current cycle safety analysis parameter document 1040 psia (nominal) 3% (accumulation) 3% (accumulation) includes a target analysis value of+ 3% (tolerance)
PZR Safety RV N/A 2500 psia (nominal)
+ 3%, - 2.5% (tolerance)
+ 3%, - 2.5% (tolerance) 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-2008-262 Attachment I Page 39 of 43 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-LOP 4-LOOP 3-LOCP RCS 4-LOOP LOWEST TOTAL MINIMUM RCS 4-LOOP HIGHEST TOTAL MAXIMUM PRESSURE TOTAL 3-LOOPS MIN ANALYSIS PRESSURE TOTAL 3-LOOPS 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-2008-262 Attachment I Page 40 of 43 Table 13. ST. LUCIE UNIT 1 - LOW PRESSURE SAFETY INJECTION PUMP DELIVERED FLOW Min Degraded LPSI Flow/Pump (4 Valves)
RCS TOTAL 3-LOOP PRESSURE FLOW MINIMUM (PSIA)
(GPM)
(GPM) 144.44 0
0 144.42 61 45 144.29 161 119 143.22 461 340 141.54 711 525 138.92 961 709 134.83 1211 894 129.61 1461 1078 123.24 1712 1263 115.69 1962 1447 106.95 2212 1632 96.99 2463 1817 85.78 2713 2002 73.31 2964 2187 44.47 3466 2557 10.30 3968 2927 I
Max LPSI Flow/Pump (4 Valves)
I Max LPSI Flow with Two Pumps (4 Valves)
I Min Degraded LPSI Flow/Pump (2 Valves) I RCS TOTAL 3-LOOP PRESSURE FLOW MAXIMUM (PSIA)
(GPM)
(GPM) 202.48 0
0 202.46 56 43 202.34 156 119 201.30 456 348 199.65 706 540 197.01 956 731 192.68 1206 922 187.10 1456 1114 180.25 1706 1305 172.10 1957 1497 162.61 2207 1688 151.76 2458 1880 139.52 2708 2071 125.86 2959 2263 94.14 3461 2647 56.39
- 3963 3031 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 5617 4219 RCS TOTAL 1-LOOP PRESSURE FLOW MINIMUM (PSIA)
(GPM)
(GPM) 144.44 0
0 144.37 61 30 143.98 161 79 140.64 461 225 136.41 711 347 127.72 961 469 117.05 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 I LPSI with 2 Valves and I 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-2008-262 Attachment I Page 41 of43 Table 14 Primary Loop Pressure Drop Distribution Geometry AP Geometry AP Friction Forward Reverse Flow Reference #
Station AP Flow SG Inlet to SG Outlet 39.9432 8.7779 11.8452 27 Assumed to be the Across RCP 72 / 80 N/A N/A 29sameascurrent 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-2008-262 Page 42 of 43 Appendix A - Calculation of Fuel Assembly Grid Weight and Surface Area REFERENCES
/
L-2008-262 Page 43 of 43
- 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 -HPSI 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 1-0120051, 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. Lucie Drawing 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.
- 20. AREVA Drawing 5041824, Cage Assembly, Revision 1 (Proprietary)
- 21. St. Lucie Drawing 8770-13348, General Arrangement (Steam Generators), Rev. 1.
- 22. FPL Letter NIF-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.
27.
31.
L-2008-262 Page 1 of 47 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 I a.
For rated power conditions (Current):
- 1. 8. Primary and Secondary Flow rates:.....
il, *
- 1** 'I t
/*,
i!'@]*,
1.1.8.1.
Core flow Ref. 3, Attach. 2.
n :+1,0 gp a d mi gpmi 412,000 Ref. 6, Items 9 and 8 for fo s3 50 0 uncertainty and min flow.
1.2.8.2.
Main coolant pumps 97,500 (2A1I)'
96,000 (2A2)
Ref. 6, Table 2 RCP Pump Test Data 95,000 (2B 1) 94,000 (2B2) 1.3.8.3.
Steam flow See Item Ia
.7.1 1.4.8.4.
Feedwater flow See Item l a ibm/hr7.
7.1 1.5.8.5.
SG recirculation Power %CiNt ratio/boiler section flow Ratio Power-20 18.41 50 7.91 Ref8
%CircRatio 70 5.42 90 3.96 100 3.46 2.9. Primalry and Secondary Pressures:
/
,.....,,o '...*,
N 2.1.9.1.
Pressurizer Nominal Operating Pressure is 2250 psia. Pressure range is 2225 to 2275, with Unc: +/- 45 Normal, + 90 Accident.
L-2008-262 Page 2 of 47 Item Parameter -Description Units Value Reference Comments No.
2.2.9.2.
Core inlet Based on 2250 psia core outlet psia 2286 and 35.5 psi core pressure drop (UFSAR Table 4.4-4).
2.3.9.3.
Core outlet Assumed to be the same as the pressurizer.
2.4.9.4.
Reactor coolant pump discharge Assume a I psi pressure drop psia 2287 from RCP discharge to core inlet.
2.5.9.5.
Steam generator dome SG outlet pressure from S886.81 Refs. 8 and 15 benchmark heat balance plus psia 8dP to upstream of flow restrictor S2.6.9.6.
T urbine control valve in let ps aSee Item I a-7.3
':2.7 Detailed primary loop pressure drop Ltral sme 0
Gtb distribution pi13 below Lae~f 1plugging.Later 3.10.
Primary and Secondary Temperatures:
3.1.10.1.
Hot leg Assumed to be the same as the OF60----
core outlet temperature since
°F 600the Rx vessel does not have upper head injection.
3.2.10.2.
Cold leg OF 549 Ref. 6, Item 6.
Tcold temperature at full Unc: +/- 3°F power.
3.3.10.3.
Core outlet Based on Tcold of 549F and OF 600 Ref. 3, Attach. 3 Tave of 574.5F.
3.4.10.4.
Upper Head Assumed to be the same as the core outlet temperature since the Rx vessel does not have OF 600 i 4.11.
Water levels in the pressurizer and steam generators,
L-2008-262 Page 3 of 47 Item Parameter -Description Units Value Reference Comments No.
4.1.11.1.
Pressurizer Ref. 6, Attachment #1,
% Tap Span See Figure 1 Figure 3.
S4.2.11.2.
Steam Generators in 411.3 Ref. 8 Level above tubesheet 5.12.
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 fobypass breakdown.
core flow rate.
5.1.12.1.
Outlet nozzle clearances Ref 7, Table 4.4-3 and Ref Assume bypass breakdown percent 1.12 R,
Table 4.4-3 documented in Unit I UFSAR S1, Figure 4.4-6 due to unit similarities.
5.2.12.2.
Downcomer to upper head Ref. 7, Table 4.4-3 and Ref documented in Unit 1 UFSAR percent 01, Figure 4.4-6 due to unit similarities.
5.3.12.3.
CEA shrouds Equivalent to a fraction of the leakage through guide tubes percent N/A (item la.5.5.1). This has not
_____________been quantified.
[5.4.12.4.
Upper head to upper plenum be uniid (guide structure holes) percent N/A This has not been quantified.
5.5.12.5.
Core bypass (guide tubes, barrel-baffle)
{
Assume bypass breakdown Ref 7, Table 4.4-3 and documented in Unit 1 UFSAR Ref 1, Figure 4.4-6 due to unit similarities.
5.5.2.12.5.2.
Barrel-baffle RAssume bypass breakdown percent 0.47 Ref 7, Table 4.4-3 and Ref documented in Unit 1 UFSAR 1, Figure 4.4-6 due to unit similarities.
6.13.
Steam generator recirculation ratio Power-
%CircRatio See Item Ia 1.5 I7.14.
Heat balance information suchi as:
L-2008-262 Page 4 of 47 Item Parameter -Description Units Value Reference Comments No.
7.1.14.1.
Feed and steam flows
/11,905,010 Ref 15 Benchmark Heat Balance ibm/hr 11,806,740 7.2.14.2.
Feedwater temperature OF 435 Ref. 15 Benchmark Heat Balance 7.3.14.3.
Turbine inlet pressure.
psia 852.7 Ref. 15 Benchmark Heat Balance, Turbine Inlet Valve
- 1.
Plant Operating Conditions lb.
For EPU conditions.
- 1. Primary and Secondary Flow rates:
L.1. C ore flow R ef, 3, A ttach. 2.Mi mu fl w s37,0 gpm 412,000 Ref. 3, Attach. 1, Item 8 for gm min flow.
gm 1.2. Reactor coolant pumps 97,500 (2A 1) gpm 96,000 (2A2)
Ref 3, Attach #1, Table 2.
RCP Pump Test Data gpm 95,000 (213 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 Ref 17
%CircRatio 50 7
c9p 75 4.40 100 3.02
- 2.
Primary and Secondary Pressures (absolute, I***:
pressures):
WW"WWi;
- N t
- 2. 1. Pressurizer
/.Ref.
3, Attach #1, Item 4.
Range: 2225 to 2275 psia.
psia 2250 Ref. 3, Item D. 17 for Uric.: + 45 psi normal, unetiny+
90 psi harsh.ucran.
L-2008-262 Page 5 of 47 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
- b. 7.3 2.7 Detailed primary loop pressure drop Table 13 distribution psi belowTable Ref, 21 Later Assumes 10% SG tube 13 plugging. Later belowLater
- 3.
Primary and Secondary Temperatures:
3.1.3.1 Hot leg Ref. 19Safety analysis will Assumes 10% SG tube plugging.Safety analysis will
°F 606.0Later determine value during determine value during EPU EPU analysis.
analysis.
3.2.3.2 Cold leg 551 Ref. 3, Attach. 1 Items 6.
Corresponds to 100% Power.
OF3Unc:
+/- 3F Ref. 3, Attach. 1, Item 7 for Tcold at zero power is 532F.
Tcold.
3.3 Core outlet Safety analysis will Assumes 10% SG tube SafLa 9 etye aalyi wril plugging.Safety analysis will Later607.9 determine value during determine value during EPU EPU analysis.Ref. 19 analysis.
3.4 Upper Head Assumed to be the same as Ref. l9Safety analysis will vessel outlet. Assume to be the same as the core outlet F
606.0Later determine value during temperature since the Rx EPU analysis.
vessel does not have upper head injection.
4 Water levels in the pressurizer and steam generators 4.1 Pressurizer
% Tap Span See Figure 1 Ref. 3, Attachment #1,
L-2008-262 Page 6 of 47 Item Parameter -Description Units Value Reference Comments No.
below Figure 3.
4.2 Steam Generators in 411.3 Ref, 8 Level above tubesheet 5
Leakage flows:
% of vessel 3.7 Ref 3, Item D.
flow 5.1 Outlet nozzle clearances ercent 112 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 ercent 0.16 Ref. 7, Table 4.4-3 and Ref Assumed to be similar to p
1, Figure 4.4-6 current operating value.
5.3 CEA shrouds percent N/A This has not been quantified.
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 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 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 7
Heat balance information such as:
7.1 Feedwater and steam flows 13,345,230 Draft Heat BalanceWill be Ibm/hr 13,246,890L Ref, 16Later provided when finalized ater 7.2 Feedwater temperature OF 436.lLater Ref. 16Later Draft Heat BalanceWill be provided when finalized 7.3 Turbine inlet pressure.
Draft Heat Balance, psia 853. 1Later Ref. 16Later Turbine Inlet ValveWill be provided when finalized
- 2.
Analysis Topical Reports 1.2.Topical Report on the licensing analysis See See See References provided of record for LOCA at rated power and Comment Comment See Comment below applicable to rated EPU conditions.
power:
L-2008-262 Page 7 of 47 Item Parameter -Description Units Value Reference Comments No.
CENPD-132, through Suppl. 4-P-A, "Calculative Method for the CE Nuclear Power Large Break LOCA Evaluation Model",
March 2001 ;
CENPD-137, through Suppl. 2-P-A, "Calculative Method for the ABB CE Small Break LOCA Evaluation Model", "April 1998.
No new Topical Reports for EPU analyses. Analysis results
-are in the UFSAR.
Safety System Logic, Setpoints and Delay
- 3. Times Critical Safety Parameters List (also called
!*i I
N fr"Groundrules document") for the last reload i**
!I l
1.6. ESFAS See Table 5 See Table 5 See Table 5 See Table 5 2.7. RPS See Table 5 See Table 5 See Table 5 See Table 5 3.8. SGIS/MSIS See Table 5 See Table 5 See Table 5 See Table 5 4.9. PORV See Table 5 See Table 5 See Table 5 See Table 5 5.10.
SRV.
See Table 5 See Table 5 See Table 5 See Table 5
- 4.
Primary and Secondary Pressure Drops 1.3.Primary side pressure drop distribution with corresponding flow rate, including leakage Later Later Later Later flows (from design data or vendor analyses).
L-2008-262 Page 8 of 47 Item Parameter -Description Units Value Reference Comments No.
2.4. 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 1.8. Number of assemblies N/A 217 Ref, 1, Table 4.2-10 2.9. Dimensions Array: 16 x 16, Pitch:
Ref. 1, Table 4.2-10, and Thpicisteumo7.2 N/A 8.180 in, Figures 4.1-2, 4.2-6.
and 0.208 = 8.180 in.
Length:
Also, Ref 13.
158.5 in 3.10.
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.
4.11.
Vessel pressure drops Current values:
a) Inlet nozzle & 90 degree a)d) 5.0
- turn, psi b)e) 10.4 Ref 1 Table 4.4-4 b) Downcomer, lower plenum, c)f) 13.4 R
support structure, d)g) 6.7 c) Fuel assembly, d) Fuel assembly outlet to outlet nozzle.
5.12.
Bypass and leakage flows
% of total See item See item la.5.5 above Similar to Item Ia.5.5 above.
flow la.5.5 above 6.13.
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.
7.14.
Number and location of guide tubes.
5 guide tubes N/A per assy.
Ref. 1, Section 4.1, and Fig.
See Fig. 3 4.1-2 for location.
below for I
L-2008-262 Page 9 of 47 Item Parameter -Description Units Value Reference Comments No.
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:
1.12.
Reactor vessel and internals (identification of all core bypass flow paths See Table 3 and flow rates, including upper plenum or head to downcomer, if available).
s 2.13.
Primary loop piping (hot leg, cold leg, See Table 3 puvvp suction) 3.14.
Reactor coolant pumps See Table 3 4.15.
Steam generators and internals (U-tube lengths, separators, inlet and outlet plenum, See Table 3 etc.), (TH Design Report) 5.16.
Pressurizer, surge line, spray lines, safety and relief valves and connecting lines, See Table 3----
etc.
6.17.
Main steam lines out to the turbine stop valves, including safety and relief valves and--Se Tal 3----
connecting lines, main steam isolation valves, flow restrictors, etc.
7.1t8.
M ain feedwater lines from the isolation--
Se Tal 3 valves to the steam generator inlet.
8.19.
Auxiliary feedwater lines and feedwater--Se Tal 3----
pump type, configuration and capacity.
II
L-2008-262 Page 10 of 47 Item Parameter -Description Units Value Reference Comments No.
9.20.
Safety injection equipment including SITs, high and low pressure injection See Table 3 systems and connecting piping.
10.21.
Charging and letdown system (CVCS).
See Table 3 1 1.22. Residual heat removal system.
See See Item 6.9 for LPSI System.
Coment.--
LPSI and RHR are the same Commentssystem.
- 7.
Reactor Vessel Internals Weight and surface area of reactor vessele internal structures:
1915.
Core support barrel 136,600I /
Includes upper, center, and 1126 Inside lower portions of the core Lbs / sq. ft.
6110 outside Ref. 20Ref. 9, Sect. 3.2 support barrel; upper and 136,600/lower flange; inner and outer Later0 nozzle areas.Dry weight. Wet Laterweight equals to 119,5 00 Ibs.
2.16.
Core shroud 34,000 /
Includes vertical and' 594 Inside horizontal surfaces of the core Lbs /sq. ft.
867 outside Ref. 20Ref. 9, Sect. 3.2 sh o d Dr weg t W t 33,800 /
weight equals to 29,600 lbs.
Later 3.17.
Upper andL lower core support plates Includes top and bottom 8,000 /
surfaces; surface areas inside Lbs / sq. ft.
260Later /
Ref. 20---
the holes of the plate.Lower Later core plate included below for weight of core support assy.
4.18.
Fuel alignment plate (Upper Core Plate) 9,900/331 Includes top and bottom Lbs /sq. ft.
9,900 / 331 Ref. 20---
surfaces; surface areas inside Later /Later the holes of the plate.---
5.19.
Upper guide structure 120,000 /
Includes CEA shrouds with Lbs / sq. ft.
7,120 Ref. 20Ref. 9, Sect. 3.2 extensions; total UGS plate, 122,200 /
flange, beam, & cylinder
L-2008-262 Page 11 of 47 Item Parameter -Description Units Value Reference Comments No.
Later areas; total fuel alignment plate area (Neglects guide tubes).Dry weight. Includes the FAP, CEA shrouds and shroud extensions. Wet weight equals to 106,900 lbs.
6.20.
Core support assembly Includes vertical webs; 45,500 /
flanges; cylinder; columns; Lbs /sq. ft.
119345,500 Ref 20Ref 9, Sect. 3.2 core support plate; bottom LbLater plate.Dry weight. Includes the lower core plate. Wet weight equals to 39,800 lbs.
7.21.
Flow skirt Includes top and bottom L bs /sq. ft.
3,600/223 Ref, 20Ref 9, Sect. 3.7.1 surfaces; surface areas inside 5L000c/ ---
the holes of the plate.ldentified as flow baffle.
8.22.
Control element assembly (CEA) 48,000 /
shrouds.
Lbs sq. ft.
1826 Inside Ref. 20---
---Does not include shroud 2100 outside extensions.
Later / Later 9.23.
Shroud extensions 10,400 /
866 Inside Lbs I sq. ft.
1035 outside Ref. 20---
Later / Later 10.24. Grid assemblies 18.5 Top grid = 2 lbs, 8 spacers @
Lbs q. t.
er ~id'O9 ef.20Rf ],abl 4.-10 1.8 Ibs each, bottomn grid = 2.6 Lb
/sq f.
per Grid 19 Rfl0e.1Tbe421 bs.Each assembly has 9 grids Later for 217 assemblies.-
- 8.
Steam Generator Internals 1.3. Weight of stear generator tube sheet and,.
surface area of tube sheet exposed to primary side fluid.
1.1.3.1.
Weight of Tube Sheet Ibm 93,230 Ref 8 Weight with integral forged
L-2008-262 Page 12 of 47 Item Parameter -Description Units Value Reference Comments No.
lower cylindrical ring and cladding 1.2.3.2.
Surface area of Tube Sheet ft2 Later Later Later (Primary Side) 2.4. Weight and surface area of steam generator*,l,
- ll wrapper.
,?!
2.1.4.1.
Weight of SG wrapper Ibm 34,730 Ref. 8 Includes wrapper roof 2.2.4.2.
Surface area of SG wrapper ft2 Later Later Later
- 9.
Steam Generator Fluid Volumes 1.6. Inlet plenum ft3 338.4 Ref 8 Includes Manway 2.7. Outlet plenum ft3 332.0 Ref. 8 Includes Manway 3.8.Active and 1230.0 inactive (within tube sheet) tubes n
41.3 4.9.Number of steam generator tubes 8999 Ref. 8 5.10.
Length of shortest and longest ft Later Later Later
- 10.
Steam Generator Parameters 1.3. Inventory and recirculation ratio versus load Later Later Later Later (essential at rated power conditions) ater
_ater 2.4. SG flow areas, K-factors and flows Later Later Later Later
- 11.
MS Line Flow Restrictor
L-2008-262 Page 13 of 47 Item Parameter -Description Units Value Reference Comments No.
3.791 to 1.2.Restrictor flow area ft2 3.803 per Re3,ScinE2ad24 OultNzeAr, SG, R.3,ScinE2an24 FlowO leVenturiN zlArea~ra 2.27 per SG
- 12.
HSteam Generator and Reactor Vessel 1.3. 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 2.4. Volume versus height for the reactor vessel See Table 6 See Table 6 Ref 1, Table 4.4-8 with internals installed
- 13.
Reactor Coolant Pump Rated Conditions 1.15.
Head The value is the average of the ft296.75 Ref. 3, Item B.7.
four pump-specific values (303, 296, 293 & 295 ft) 2.16.
Flow The value is the average of the four pump-specific values gpm 87,750 Ref 3, Item B.8.
(8,0
-8,0900 (85,000 - 87,500 - 91,000 &
87,500 gpm) 3.17.
Torque The value is the average of the Ref. 3, Item D.6.
four pump-specific values (33,860 - 34,000 - 34,720 &
33,230 ft-lbf) 4.18.
Speed rpm 900 Ref. 3, Item D.4.
Synchronous speed 5.19.
Density The value is the average of the ft 3 four pump-specific values lbm/ ft' 47.5 Ref. 3, Attach.l1, Item 14 fu ui-pcfcvle (47.3, 47.4, 46.9 and 48.4 Ibm/
Sft3
)
6.20.
Homologous pump curves (four N/A See Table 7 Ref. 3, Table 2.
L-2008-262 Page 14 of 47 Item Parameter -Description Units Value Reference Comments No.
quadrant) 7.21.
Pump inertia and friction (coefficients of Uncertainty value of+ 1%
polynomial in pump speed)
Ibm-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.
8.22.
Coolant primary system fluid volume ft3 112 Ref. 10 within pump 9.23.
RCP metal mass, excluding motor lbs 75,000 Ref. 10 Dry weight.
10.24. 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.
11.25.
Pump power to primary fluid 14.2 MWt (nominal),
Ref, 3, Attach. 1, Item 12 20 (max) 12.26. Coastdown characteristics N/A Figure 2 Ref 1, Figure 15.3.2-1 13.27. Pump trip setpoints N/A Overcurrent Ref. 12 Overload Trip 14.28.
Pumnp time delays and logic N/A N/A N/A No safety related RCP trips.
- 14.
Core Cooling System 1.6. HPSI and LPSI delivery curves See Tables 8, Ref. 3; Attach. 1, Tables 3, gpm 9, 10, 11 4, 5,6' 2.7. SIT total volume 3
1Four tanks, each with this et 1855 Ref. 1, Table 6.3-1 capacity.
3.8. SIT initial pressure and liquid volume
- (500 to
- psia 650 + 15) 0 Ref. 3, Item E.10 TS ranges for SIT pressure W
ft3
- (1420 to 0
Ref 3, Item E.9 and liquid volume' 1556 + 32) 4.9. CST minimum capacity gal 276,200 Ref. 3, Attach. 1, Item 84 5.10.
Charging pump flow versus pressure Reciprocal pump. Flow is per gpln 40 (nominal)
Ref. 3, D.27 charging pump. Nominal to 49 value does not include 4 gpm
L-2008-262 Page 15 of 47 Item Parameter -Description Units Value Reference Comments NO.
(maximumn) for RCP bleed-off.
35 minimum, after uncertainties 15.a Control Systems Rated~power operation of the primary and
- I
- "I*,
secondary co ntrol1 sy stems for:
ii
- l *:
- ,*tI
- N 1.13.
SG water level instrumentation and Lae aeIae ae control (three-element) 2.14.
SG pressure (including bypass and Later Later Later Later ADV) 3.15.
Pressurizer heaters and sprays Later Later Later Later 4.16.
Pressurizer level Later Later Later Later 5.17.
Auxiliary feedwater Later Later Later Later 6.18.
CVCS (charging and letdown)
Later Later Later Later 15.b Control Systems 8.20.
SG pressure (including bypass and Later Later Later Later ADV) 9.21.
Pressurizer heaters and sprays Later Later Later Later 10.22. Pressurizer level Later Later Later Later 11.23.
Auxiliary feedwater Later Later Later Later 12.24. CVCS (charging and letdown)
Later Later Later Later
- 16.
Reactor Vessel Upper Head
L-2008-262 Page 16 of 47 Item Parameter -Description Units Value Reference Comments No.
Assume to be the same as the 1.2.Upper head fluid temperature at normal OF Later See item I.b.3.4 above, core outlet temperature since operating conditions.
the Rx vessel does not have uper head injection.
iL
- 17.
Essential Valve Characteristics 41Number of valves, full open flow area, forward/ reverse flow coefficients (CV's),
open/close rate, mininmum flow at rated conditions, logic for opening and closing the valves for:
S1.10.
Pressurizer PORVs See Table 12---------
S2.11.
Pressurizer safety valves See Table 12---------
S3.12.
Main steam safety valves See Table 12---------
S4.13.
Atmospheric dump valves See Table 12---------
5.14.
TCVs (turbine control valves)
See Table 12 6.15.
Turbine bypass valves See Table 12 7.16.
TSVs, (turbine stop valves)
See Table 12 8.17.
MEIVs
See Table 12---
9.18.
MSIVs See Table 12 18.
to Reactor Core Parameters 20.
1.11.
Control rod insertion versus time afterLaeL trL trL tr scrarm 2.12.
CEA worth versus insertion (with and without highest worth rod stuck out of core) 3.13.
Reactivity versus fuel temperature and Later Later Later Later reactivity versus moderator density 4.14.
Moderator temperature coefficient Later Later Later Later
L-2008-262 Page 17 of 47 Item Parameter -Description Units Value Reference Comments No.
5.15.
Typical top peaked axial power profile Later Later Later Later 6.16.
Minimum and maximum average fuel clad gap conductivity at rated power Later Later Later Later conditions 7.17.
Minimum local gap conductance as a Later Later Later Later function of LHGR 8.18.
Gap conductance Later Later Later Later 9.19.
Linear heat rate Later Later Later Later 10.20. 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 1.4. Reactor coolant pump trips (conditions to Accident analysis assumes trip pumps - automatic or manual)
Punps LOOP concurrent with LOCA, automatically and pumps are not loaded into None trip on Ref. 1, Section 15.6.5 EDGs or manually operated.
LOOP Same assumption for EPU analysis.
2.5. 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-2008-262 Page 18 of 47 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.
3.6. 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. 1, 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 coolant system (stainless steel, inconel, etc. )
1.5. Density Later Later Later Later 2.6. Specific heat Later Later Later Later
L-2008-262 Page 19 of 47 Item Parameter -Description Units Value Reference Comments No.
3.7. Thermal conductivity Later Later Later Later 4.8. Emissivity versus temperature Later Later Later Later
'Page 20 of 47 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 1 CL CL U,
a.
50 1 45 +
40 +
35 t (538.2, 33.1) 30 +
- 25 I
I I
I I
520.0 530.0 540.0 550.0 560.0 570.0 TAVE (F) 580.0 590.0 Pressurizer Volume at 63.0% Span is 914 Cu. Ft.
Pressurizer Volume at 33.1% Span is 463 Cu. Ft.
L-2008-262 Page 21 of 47 Figure 2 - RCP Cncffdnwn Note: Curve represents current analyses.
L-2008-262 Page 22 of 47 Figure 3
L-2008-262 Page 23 of 47 Figure 4
-13 T-2~
-lSi -11 F-19 P-1 FEED E-20 X13 FEE 1~
53 X12 T47 X,22 USO I1In X23 U35 X7O T29j
ý3 FEED G-7 FEED W-I y-6 FEED N,18 FEED S-lB 1S 752 X04 TAS >2 U38 T'72 X33 W 2 )Y52 E D W-li FEED L-12 FEED C,16 NAS IIEED E-4 FEED I
I I
I Th~U52I UI~I rI Xni I I 11 6411 1 vv;U 3 -21 1FEED IE2X-9
L-2008-262 Page 24 of 47 Table 1 (Later)
L-2008-262 Page 25 of 47 Table 2 (Later)
L-2008-262 Page 26 of 47 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 II1A, Rev. 11 2998-455, Rev. 6 2998-G-078, Sheet II1B, Rev. 10 2998-457, Rev. 8 2998-G-078, Sheet 11 IC, Rev. 13 2998-G-078, Sheet IllD, 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 2998G-6125, 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 SI-N-7, Rev. 15 2998-G-125, Sheet SI-N-8, Rev. 18
L-2008-262 Page 27 of 47 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-1 7, 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-124i 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. II 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-l10, 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-2008-262 Page 28 of 47 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 C
Notes: Measured from bottom of fuel assembly to top of grid.
L-2008-262 Page 29 of 47 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)
> 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
+/- 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 1 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-2008-262 Page 30 of 47 Table 6 I1.
2,0 Ca CEA Top
L-2008-262 Page 31 of 47 Tr
L-2008-262 Page 32 of 47 Table 7 Table 2 - Reactor Coolant Pump Homologous Curves VALPHA HAN HVN BAN BVN VALPHA HAD HVD BAD BVD 0.0000 1.5800
-1.4200 0.7700
-1.4500 0.0 1.5800 1.2200 0.7700 1.3150 0.1000 1.5000
-1.2150 0.8020
-1.1120
-0.1 1.6600 1.2850 0.8100 1.3800 0.2000 1.4200
-1.0820 0.8450
-0.8720
-0.2 1.7600 1.3450 0.8800 1.4500 0.3000 1.3700
-0.9120 0.8660
-0.6480
-0.3 1.8700 1.4400 0.9800 1.5100 0.4000 1.3300
-0.7280 0.8850
-0.4420
-0.4 2.0000 1.5500 1.0900 1.5800 0.5000 1.2950
-0.4940 0.9100
-0.2700
-0.5 2.1300 1.7200 1.2350 1.6400 0.6000 1.2700 0.0000 0.9300 0.2600
-0.6 2.3000 1.9300 1.3900 1.7200 0.7000 1.2400 0.2080 0.9530 0.4300
-0.7 2.4700 2.1800 1.5800 1.8300 0.8000 1.1820 0.4350 0.9730 0.6130
-0.8 2.7000 2.4900 1.7850 1.9600 0.9000 1.1050 0.7080 0.9890 0.8000
-0.9 2.9300 2.8100 2.0400 2.1200 1.0000 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 0.00.0000 0.4330 1.2200
-1.4400 1.3150 0.0 0.4330
-1.4200
-1.4400
-1.4500 0.10.1000 0.4740 1.1820
-0.9200 1.2450
-0.1 0.3430
-1.7150
-1.6600
-1.8500 0.20.2000 0.5020 1.1400
-0.6300 1.1800
-0.2 0.0112
-1.9600
-1.9100
-2.2000 0.30.3000 0.5120 1.0850
-0.4200 1.1100
-0.3
-0.2460
-2.1500
-2.1900
-2.5200 0.40.4000 0.5240 1.0450
-0.2500 1.0420
-0.4
-0.5130
-2.3400
-2.4900
-2.8500 0.50.5000 0.5460 1.0000
-0.1000 0.9750
-0.5
-0.8300
-2.5200
-2.8300
-3.1500 0.60.6000 0.5830 0.9500 0.0200 0.9050
-0.6
-1.0350
-2.6900
-3.2400
-3.4900 0.70.7000 0.6410 0.9000 0.1300 0.8170
-0.7
-1.6000
-2.8100
-3.6000
-3.8400 0.80.8000 0.7120 0.8700 0.2510 0.7280
-0.8
-2.0500
-2.9300
-4.0500
-4.2300 0.90.9000 0.8000 0.8650 0.3900 0.6280
-0.9
-2.5500
-3.0100
-4.5400
-4.6100 1.01.0000 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-2008-262 Page 33 of 47 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-2008-262 Page 34 of 47 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 BI 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 Table 9 (Sheet I of 2)
L-2008-262 Page 35 of 47 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-2008-262 Page 36 of 47 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 Table 10 SL-2 SAFETY INJECTION DATA NO FAILURE IN ECCS EFFECTIVE FOR NON-LOCA ANALYSIS
L-2008-262 Page 37 of 47 (All Pumps On)
MAXIMUM MINIMUM RCS Flow to RCS Flow to Pressure Loop Al, A2 Pressure Loop Al, A2 (psia)
B1 or B2 (psia)
B1 or B2 1408 0
1165 0
1399 28 1158 23 1382 55 1142 45 1337 83 1105 68.
1230 110 1068 90 1160 138 1008 113 1070 165 929 135 948 193 824 158 819 220 711 180 680 248 591 203 511 275 445 225 334 303 290 248 184 700 166 261 178 800 162 262 173 850 157 262 166 950 150 263 158 1050 143 264 149 1150 135 370 139 1250 125 660 128 1350 116 825 116 1450 105 990 103 1550 93 1080 89 1650 81 1170 74 1750
.67 1260 58 1850 52 1350 39 1900 35 1440 20 2000 18 1530 0
2050 0
1620 Table 11 (Sheet 1 of 2)
SL-2 UFSAR ECCS PERFORMANCE DATA ONE EMERGENCY GENERATOR FAILED TO START
L-2008-262 Page 38 of 47 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 Table 11 (Sheet 2 of 2)
SL-2 UFSAR ECCS PERFORMANCE DATA ONE EMERGENCY GENERATOR FAILED TO START
L-2008-262 Page 39 of 47 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 Table 12 Component Data Required Component Flow Diagram Component Information Pressurizer PORVs V 1474 V1475 2998-G-078 Sheet 108 Rev. 5 1 2998-18810 Rev. 3
L-2008-262 Page 40 of 47 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 2998-G-079 Sheet 2, Rev.35 2998-2184 Rev. 10 FCV-08-641 2998-31, Rev 17 FCV-08-642 FCV-08-643 Main Feed Isolation Valves HCV-09-IA 2998-G-080 Sheet 2A Rev. 43 2998-9486 Rev. 4 HCV B 2998-9487 Rev. 4 HCV-09-2A HCV-09-2B Main Steam Isolation Valves
L-2008-262 Page 41 of 47 HCV-08-1A 2998-G-079 Sheet 1, Rev. 41 2998-1011 Rev. 3 Sheet 1/9 HCV-08-IB 2998-1012 Rev. 0 Sheet 2/9 Miscellaneous Components V09107 V09108 SE-09-2 2998-G-080 Sheet 2B Rev.36 MV-09-9 V09119 V09120 V09123 V09124 SE-09-3 MV-09-10 V09135 V09136 V09139 V09140 SE-09-4 MV-09-11 V09151 V09152 SE-09-5 MV-09-12 V09157 V09158 V3225 V3624 V3258 V3227 V3215 2998-20110 Rev. 1 2998-741 Rev. 3 2998-13008 Rev. 3 2998-13006 Rev. 1 2998-13009 Rev. 2 2998-19745 Rev. 2 2998-1872 Rev. 6 2998-5616 Rev. 0 2998-3033 Rev. 4 2998-742 Rev. 2 2998-20110 Rev. 1 2998-741 Rev. 3 2998-13008 Rev. 3 2998-13006 Rev. 1 2998-13009 Rev. 2 2998-19745 Rev. 2 2998-1872 Rev. 6 2998-5617 Rev. 0 2998-3033 Rev. 4 2998-742 Rev. 2 2998-752 Rev. 5 2998-751 Rev. 2 2998-13007 Rev. 1 2998-13008 Rev.3 2998-13009 Rev. 2 2998-19745 Rev. 2 2998-1871 Rev. 7 2998-5617 Rev. 0 2998-3033 Rev. 4 2998-742 Rev. 2 2998-13007 Rev. 1 2998-13008 Rev.3 2998-13009 Rev. 2 2998-19745 Rev. 2 2998-1871 Rev. 7 2998-5616 Rev. 0 2998-3033 Rev. 4 2998-742 Rev. 2 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-G-078 Sheet 132 Rev. 9 V3614
L-2008-262 Page 42 of 47 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. I 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 FE-3321 V3766 8770-14084 Rev. 1 8770-14099 Rev. I 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 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
L-2008-262 Page 43 of 47 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-lB Suction Stabilizer for CHG PP 2B Pulsation Damper CHG PP 2B V2168 V2464 V2316 SS-02-IC Suction Stabilizer for CHG PP 2C Pulsation Damper for CHG PP 2C V2167 V2339 FE-2212 V2429 2998-G-078 Sheet 130A Rev. 19 2998-G-078 Sheet 121A Rev. 31 2998-G-078 Sheet 122 Rev. 25 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 2998-9070 Rev. 2 2998-9069 Rev. 2 8770-14084 Rev. ]
8770-14099 Rev. ]
2998-1031 Rev. 5 2998-560 Rev. 2
L-2008-262 Page 44 of 47 V2523 V2462 V2535 V2598 V2485 V2433 SE-02-2 V2484 V2432 SE-02-1 V2593 V2515 V2516 V2522 V2341 V2342 (Letdown Heat Exchanger)
LTDN HT EXCH V2347 PCV-2201Q V2349 FE-2202 V2358 (Purification Filter)
Purif Filter 2A V2360 V2520 V2359 V2370 2998-G-078 Sheet 120 Rev. 17 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 2998-1037 Rev. 1 2998-17025 Rev. 0 2998-2584 Rev. 6 2998-590 Rev. 5 2998-17042 Rev. 1 2998-1029 Rev. 2
L-2008-262 Page 45 of 47 (Purification Ion Exchanger)
Purif IX 2A V2378 V2382 V2395 (Letdown Strainer)
S2900 V2415 V2418 V2452 (Purification Filter)
Purif Filter 2B FE-8011 FE-8021 V 1442 V 1249 PCV-11OOF V1444 V1477 V1479 V 1476 V 1478 V1443 PCV-1100E V1248 V1441 FE-01-2 FE-01-1 FE-09-2A FE-09-2B FE-09-2C MV-08-14 MV-08-15 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 2998-G-078 Sheet 108 Rev. 5 2998-G-080 Sheet 2B Rev.36 2998-G-079 Sheet 1 Rev. 41 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 2998-13912 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
L-2008-262 Page 46 of 47 MV-08-16 MV-08-17 V08359 V08360 V09294 V09252 2998-G-079 Sheet 2 Rev. 35 2998-G-080 Sheet 2A Rev 43 2998-10621 Rev. 6 2998-10621 Rev. 6 2998-3012 Rev. 8 2998-3012 Rev. 8 2998-2143 Rev. 5 2998-2143 Rev. 5 Table 13 Current Primary Loop Pressure Drop Distribution Geometry AP Geometry AP Friction Station AP Forward Flow Reverse Flow RV Outlet to SG Outlet 26.92 10.88 9.56 SG Outlet to RV Inlet 1.00 3.62 3.62
.. U,,
(psi (ps RV Outlet to SG Outlet 33.72 13.64 12.00 SG Outlet to RV Inlet 1.24 4.54 4.54
L-2008-262 Page 47 of 47 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-0 l-JOO
- 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.
19.21.
Westinghouse Letter FPL-08-118, "Extended Power Uprate: NRC Data Request", dated 12-17-08.Westinghouse Letter PCWG-08-33, Rev. 1, "Approval of Revised Category IIP (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.