ML17264B108

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Rev 0 to Ginna Station Colr,Cycle 27.
ML17264B108
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/14/1997
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264B107 List:
References
NUDOCS 9711240147
Download: ML17264B108 (32)
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GINNA STATION COLR Cycle 27 Revision 0 CORE OPERATING LIIVIITS REPORT (COL R)Responsible manage i(/iw/ev Effective Date Controlled Copy Ho.9'7ii240i47 97iii7 PDR ADOCK 05000244DR R.E.Ginna Nuclear Power Plant Core Operating Limits Report Cycle 27 Revision 0 This report is not part of the Technical Specifications.

This report is referenced in the Technical Specifications.

TABLE OF CONTENTS 1,0 CORE OPERATING LIMITS REPORT 2.0 OPERATING LIMITS........~~2.1 SHUTDOWN MARGIN.....

~~2.2 MODERATOR TEMPERATURE COEFFICIENT

.2.3 Shutdown Bank Insertion Limit.2.4 Control Bank Insertion Limits.2.5 Heat Flux Hot Channel Factor (FQ(Z))~~2.6 Nuclear Enthalpy Rise Hot Channel Factor (F"~)2.7 AXIAL FLUX DIFFERENCE

.2.8 RCS Pressure, Temperature, and Flow Departure from Boiling (DNB)Limits 2.9 Boron Concentration

.~~~~Nucleate 3 3 3 3 4 4 5 5 3.0 UFSAR CHAPTER 15 ANALYSIS SETPOINTS AND INPUT PARAMETERS

4.0 REFERENCES

6 FIGURE 1-RE(UIRED SHUTDOWN MARGIN.FIGURE 2-CONTROL BANK INSERTION LIMITS................

8 FIGURE 3 K(Z)NORMALIZED Fo(Z)AS A FUNCTION OF CORE HEIGHT o~~~~9 FIGURE 4-AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AND TARGET BAND LIMITS AS A FUNCTION OF RATED THERMAL POWER.10 TABLE 1-UFSAR CHAPTER 15 ANALYSIS SETPOINTS AND INPUT PARAMETERS.....

11 I COLR Cycle 27, Revision 0 R.E.Ginna Nuclear Power Plant Core Operating Limits Report Cycle 27 Revision 0 1.O CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR)for Ginna Station has been prepared in accordance with the requirements of Technical Specification 5.6.5.The Technical Specifications affected by this report are listed below: 3.1.1 3.1.3 3.1.5 3.1.6 3.2.1 3.2.2 3.2.3 3.4.1 3.9.1"SHUTDOWN MARGIN (SDM)""MODERATOR TEMPERATURE COEFFICIENT (MTC)""Shutdown Bank Insertion Limit""Control Bank Insertion Limits""Heat Flux Hot Channel Factor (Fo(Z))""Nuclear Enthalpy Rise Hot Channel Factor (F"<<)""AXIAL FLUX DIFFERENCE (AFD)""RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)Limits""Boron Concentration" COLR Cycle 27, Revision 0

2.0 OPERATING

LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections.

These limits have been developed using the NRC approved methodologies specified in Technical Specification 5.6.5.All items that appear in capitalized type are defined in Technical Specification 1.1,"Definitions." 2.1 SHUTDOWN MARGIN (LCO 3.1.1)(Limits generated using Reference 1)2.1.1 2.1.2 2.1.3 The SHUTDOWN MARGIN in MODE 2 with K.<<<1.0 and MODES 3 and 4 shall be greater than or equal to the limits specified in Figure 1 for the number of reactor coolant pumps in operation.

The SHUTDOWN MARGIN in MODE 4 when both reactor coolant pumps are not OPERABLE and in operation and in MODE 5 shall be greater than or equal to the one loop operation curve of Figure 1.The SHUTDOWN MARGIN required in LCOs 3.1.4, 3.1.5, 3.1.6, 3.1.8, and 3.4.5 shall be greater than the limits specified in Figure 1 for the number of reactor coolant pumps in operation.

2.2 MODERATOR

TEMPERATURE COEFFICIENT (LCO 3.1.3)(Limits generated using Reference 1)2.2.1 The Moderator Temperature Coefficient (MTC)limits are: The BOL ARO/HZP-MTC shall be less positive than+5.0 pcm/'F for power levels below 70%RTP and less than or equal to 0 pcm/'F for power levels at or'bove 70%RTP.The EOL ARO/RTP-MTC shall be less negative than-42.9 pcm/'F.where: ARO stands for All Rods Out BOL stands for Beginning of Cycle Life EOL stands for End of Cycle Life HZP stands for Hot Zero THERMAL POWER RTP stands for RATED THERMAL POWER 2.3 Shutdown Bank Insertion Limit (LCO 3.1.5)(Limits generated using Reference 1)2.3.1 The shutdown bank shall be fully withdrawn which is definedas z 221 steps.I COLR Cycle 27, Revision 0

2.4 Control

Bank Insertion Limits (LCO 3.1.6)(Limits generated using Reference 1)2.4.1 The control banks shall be limited in physical insertion as shown in Figure 2.2.4.2 The control banks shall be moved sequentially with a 100 (+5)step overlap between successive banks.2.5 Heat Flux Hot Channel Factor F Z (LCO 3.2.1)(Limits generated using References 1 and 2)2.5.1 Fo(Z)s~F J"K(Z)when P)0.5 P Fo(Z)s~F*K(Z)0.5 when P s 0.5 where: Z is the height in the core, Fo 2.45, K(Z)is provided in Figure 3, and THERMAL POWER P RATED THERMAL POWER 2.6 Nuclear Enthal Rise Hot Channel Factor F" (Limits generated using Reference 1)(LCO 3.2.2)2.6.1 F" F"~*(1+PF*(1-P))where: FATP PF~0.3, and THERMAL POWER P RATED THERMAL POWER 2,7 AXIAL FLUX DIFFERENCE (LCO 3.2.3)(Limits generated using References 1 and 3)2.7.1 2.7.2 The AXIAL FLUX DIFFERENCE (AFD)target band is+5%..The actual target bands are provided by Procedure RE-11.1.The AFD acceptable operation limits are provided in Figure 4.COLR Cycle 27, Revision 0 2.8 RCS Pressure Tem erature and Flow De arture from Nucleate Boilin Li~i (ICII 3 4 i)(Limits generated using Reference 4)2.8.1 2.8.2 2.8.3 The pressurizer pressure shall be z 2205 psig.The RCS average temperature shall be z 577.5 F.The RCS total flow rate shall be a 170,200 gpm (includes 4%minimum flow uncertainty per Revised Thermal Design Hethodology).

2.9 Boron

Concentration (LCO 3.9.1)(Limits generated using References 1 and 5)2.9.1 The boron concentrations of the hydraulically coupled Reactor Coolant System, the refueling canal, and the refueling cavity shall be z 2300 ppm.3.0 UFSAR CHAPTER 15 ANALYSIS SETPOINTS AND INPUT PARAMETERS The setpoints and input parameters for the UFSAR Chapter 15 accident analyses are presented in Table 1.The values presented in this table are organized based on system and major components within each system.The failure of a component or system to meet the specified Table 1 value does not necessarily mean that the plant is outside the accident analyses since: (1)an indicated value above or below the Table 1 values may be bounded by the Table 1 values, and (2)the setpoint or parameter may not significantly contribute to the accident analyses final results.The major sections within Table 1 are: 1.0 Reactor Coolant System (RCS)2.0 Hain Feedwater (HFW)3.0 Auxiliary Feedwater (AFW)4.0 Hain Steam (HS)System 5.0 Turbine Generator (TG)6.0 Chemical and Volume Control System (CVCS)7.0 Emergency Core Cooling System (ECCS)8.0 Containment

9.0 Control

Systems 10.0 Safety System Setpoints 11.0 Steam Generators COLR Cycle 27, Revision 0

4.0 REFERENCES

2.3.4.5.WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Hethodology, July 1985.WCAP-10054-P-A and WCAP-10081-NP-A,"Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.WCAP-10924-P-A, Volume 1, Rev.1, and Addenda 1,2,3,"Westinghouse Large-Break LOCA Best-Estimate Methodology, Volume 1: Model Description and Validation," December 1988.WCAP-10924-P-A, Volume 2, Rev.2, and Addenda,"Westinghouse Large-Break LOCA Best-Estimate Methodology, Volume 2: Application to Two-Loop PWRs Equipped with Upper Plenum Injection," December 1988.WCAP-10924-P-A, Rev.2 and WCAP-12071,"Westinghouse Large-Break LOCA Best Estimate Methodology, Volume 2: Application to Two-Loop PWRs Equipped With Upper Plenum Injection, Addendum 1: Responses to NRC guestions," December 1988.WCAP-10924-P, Volume 1, Rev.1, Addendum 4,"Westinghouse LBLOCA Best Estimate Methodology; Model Description and Validation; Model Revisions," August 1990.[Approved by NRC SER dated 2/8/91]WCAP-8385,"Power Distribution Control and Load Following Procedures-Topical Report," September 1974.WCAP-11397-P-A,"Revised Thermal Design Procedure", April 1989.WCAP-11596-P-A,"gualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988.COLR Cycle 27, Revision 0 3 0 l1l 2 0'm1 x V)(1500.1.45)

(1 500, 1.00)ACCEPTABLE OPERATION ONE LOOP OPERA'nON~O LOOP OP ERAllON UNACCEPTABLE OPERATION (0.2.45)(0, 1.80)1500 1000 500 COOLANT gpRON CONCENTRATION (ppm)FIGURE I REQUIRED SHUTDOWN MARGIN COLR Cyc1e 27, Revision 0 220 3 200~~380$<6O o.$40~120.a 100 N 80 CL~~60 ca 40 o 20 0 0 (0, 164 (0,53)10 B Bank 1834~'666,'100, 184)CB ank ank DB (30, 20 30 40 60 ,60 70 80 90 t00 Core Power (Percent of 1520 Mg/T)*The fully withdrawn position is defined as a 221 steps.FIGURE 2 CONTROL BANK INSERTION LIMITS~COLR Cycle 27, Revision 0 0.2 N~1.0 u0.8 U)C'65 e 06 0 6$~~K K 04 CP N~~l5 F02 0 Tota(Fz=2.460~E't~K 0.0 1.0 11.783 1.0 0.0 0,0 2.0 4.0 6.0 8.0 Elevation (ff)10.0 11.783 FIGURE 3 K(Z)-NORMALIZED Fo(Z)AS A FUNCTION OF CORE HEIGHT COLR Cyc1e 27, Revision 0

(-11,90)DO NOT OPERATE IN THIS AREA WITH AFD oUTSIOE THE TARCET S~(11/0)80~O CI 40 I-Cl l~ACCEPTABLE OPERATION YAH AFD"""""""" OUTSaE THE TARO ET BAND WITH<<1 fa PENALTY DEMATION TNE (Q1,60)P1,60)ACCEPTABLE

~~~~~y 0~OPERATION 20 0-20-10 0 10 20 30 AXIAL FLUX DIFFERENCE

(%)FIGURE 4 AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AND TARGET BAND LIMITS AS A FUNCTION OF RATED THERMAL POWER COLR 10 Cyc'te 27, Revision 0 Table 1: UPSAR Chapter 5 Analysis Setpoints and ut parameters Item 4 Item/Name Value Remarks: 1.0 Rcoctor Coolant System (RCS)Upper head volwre, ft'pper Plenum volune, fto Top of fuel volune, fto Inlet nozzle(s)volune, total of two, ft outlet nozzle(s)volune, total of two, ft Active fuel volrire, ft3 Bottom of fuel volurre, fto Lower PLenrgr volune, ftc Downcomer volunc, above bottom of cold leg, ft Downcomer, lower core plate to elevation of the bottom of the cold Leg volune, fts Barrel baffle, lower core plate to upper core plate volrmre, ft Total volunc, fto Hot leg pipe volte per Loop vair ft>Cold leg voluae per Loop+cross over, fti RC pmp volunc per pump, f t'old leg pipe ID, In./Purrp suction ID, in.Hot leg pipe ID, in.Design pressure, psig Design temperature, F Cold Leg and Hot i.eg Centerline Elevation 300.0 580.2 50.3 43.2 37.4 367.6 11.0 514.3 138.4 278.2 128.5 2449.1 78.7 cross over=140.7 cold Leg=46.8 192 27.5/31 29 (28.969)2485 650 246'0u Above upper support plate.Bottom of upper core plate to top of upper support plate.Includes outlet holes in the barrel.Top of active fuel to bottom of upper'ore plate, inside barreL baffle.Includes nozzle forging protrusion into vessel.Does not include mating hole in barrel, this is included in the Upper PLenun volune.Bottom of fuel to top of fuel Top of Lower core plate to bottom of active fuel.Below top of lower core plate Above bottom of cold leg elevation to bottom of upper support plate Top of Lower core plate to elevation of bottom of cold Leg Top of Lower core plate to bottom of upper ccrc plate.Includes nozzles Reactor Coolant Prsrrp Head-Capacity and NPSH curves for reactor coolanz pumps/Homologous Curves Rated RC pump head and flow, ft&gpm Rated RC pump torque and efficiency 9 rated head/flow, ft-lb, fraction RCP Prmp Rated Power (hot, 556 degrees F)RCP Hotor Rated Speed, RPM Moment of inertia of pump and motor, lb-ftz RC pump heat, MMt (max/min per pump)See HS&L 252;90,000 84K efficiency at hot conditions 4842 BHP 1189 80,000 5, 4 Homologous Curves are available in RETRAH Pwp power varies with RCS terrp fram approx 4 MWt to 5 Mwt 1.2 Core COLR Cycle 27, Revision 0 Table 1: UPSAR Chapter 5 Analysis Setpoints and~ut Parameters Item 4 Item/Name Value Remarks: Rated power, HWt Reactor power uncertainty, g RTP Bypass, X Upper head bypass, g Upper head tcngerature, degrees F Heat transfer area, fthm Average core heat flux, Btu/hr ft>1520 6.5 M proprietary 590 26,669 189,440 Thimble plugs removed.High T~value.1.3 1.3.1 Fuel Assemblies Height Total, inches (length from bottom of asscnhty to top nozzle)Fuel Rod Length, inches (length from bottom of pin to top of pin)Active, inches 159.935 149.138 141.4 1.3.2 Fuel Assembly Geometry Hass of fuel, ibm Hoss of clad, ibm Humber of fuel pins per fuel assembly (FA)Ho.of Fuel Assemblies Fuel pin pitch, in.Bottom nozzle weight and votunc Top nozzle, w/insert, weight and volune Fuel Asserrhty resistance (core dP f(flow)], psi f (lb/hr)Fuel Assembly free flow area, in 105,500 25,927 179 121 0.556 9.1 lbs.31.5 in 18.15 lbs.62.9 in'ore delta P-"20 psi 9 flow~170,200 gpn 34.75 Thimble plugs removed.Single assembly.1.3.3 Fuel pin geometry Pellet diameter, in.Clad 00/IO, in./in.0.3444 0.400/0.3514 1.3 4 Control Rod 4 Instruaent Gurdc Tubes Ho.of control rod guide tubes Ho.of instrunent guide tubes Control Rod Guide tube upper part 00/ID, in./in.Instrunent Guide tube 00/ID, in./in.Guide tube lower part 00/ID, in./in.Control Rod Drop Times, maximuns, scc.Control rod maximun withdrawal rate, in./min.16 0.49/0.528

.0.395/0.350 0.4445/0.4825 Hon-LOCA 2.4 LOCA 3.0 45 Altowanccs are added to the Tech Spec allowable value COLR 12 Cycle 27, Revision 0 Table 1=UFSAR ('-rapter 5 Analysis Setpoints and ut parameters Item g Item/Name Value Remarks: Control rod maxim(rs insertion rate, pcm/sec.Control rod insertion limits Hot channel radial peaking factor Heat Flux Hot channel factor Fq 90 See COLR 1.75 2.45 1.4 pressurizer code safety valve flow capacity, Lbm/hr Code safety Code safety Spray valve Spray valve Spray valve Spray valve PORV number valve open time valve setpoint n(rmber flow capacity, gpm/vaLve setpoint-start open/fulL open time constant, sec.pORV flow capacity, Lbm/hr pORV Cv PORV open time PORV close time gackup Heaters Minimus heater capacity required for LOOP, k'M Heater bank controller type pORV setpoint[normal)open/close, psig pORV setpoint (LTOP]open/close, psig pORV blowdown characteristic Heater capacity w/bank capacity and setpoints, kif Control banks 288,000 0.8 sec seal clearing time 2485 psig 2 200 2260/2310 5 2 179,000 50 gpm/(psid)1/2 1.65 sec+transmitter 3.95 sec+transmitter 2335/2315 430 800 0 kW at 2250 psig and 400 kw st 2220 psig Full on at 2210 psig snd resets at 2220 psig 100 proportional 400 kM Rating at 2485 psig plus 3X accumulation Crosby Model HB-BP-86, size 4K26 Tolerance is+2.4X/-3X.proportional Assed value Steam flow st 2335 psig Rating is for liquid relief.Valve characteristic is quick opening see Copes Vulcan Selecting and Sizing Control Valves 8/75, page 8, Table 18 for Cv vs travel curve.LTOPs transmitter is Foxboro E11GM-HSAE1, with a time response of 1 sec (time to 90K of final value for step input)LTOPs transmitter is Foxboro E11GM-HSAE1, with a time response of 1 sec (time to 90K of final value for step input)1.4.1 pressurizer volusc(s)(100M/Ly(power)Lister, ft (100K/OX power)Steam, ft (100M/OX power)Total, ft pressurizer LD, ft-in 396/199 404/601 800 83 624 in/cladding thickness is 0.188 in COLR 13 Cyc'1 e 27, Revision 0

Table 1: UFSAR Chapter 5 Analysis Setpoints and ut parameters item 0 Xtem/Name Value Remarks: Surge line ID, in.Spray linc ID, in.Surge line volune ft 8.75 3.062 18.4 Surge line is 10 in schedule 140 1 4.2 Pressurizer Level Lower level tap elevation Upper level tap elevation pressurizer level vs X power Distance Not Leg Centerline to Lower Tap, ft Haximm level allowed for steam bubble, X 257'275'%power Level 0 X 35X 100 X 50X 10.750 87 pressurizer level is ramped linearly between these points.Not used in Chapter 15 analyses.1.5 RCS Plows, Temperature and Pressures Total reactor coolant flow, gpm (15X plugging)Total reactor coolant flow, gpm (15K plugging)Average reactor coolant tecperature, degrees F (full power/N2P)

Reactor coolant pressure, psig Reactor coolant flow uncertainty, X nominal Reactor coolant temperature uncertainty, degrees F Reactor coolant pressure uncertainty, psi DNB Limit (safety analysis limit)170,200 177,300 559 to 573.5/547 2235 a 30 1.40 Usc for non DNB Usc for statistical DNB Cycle 26 T~=561 1.6 Low Tcaperature Overprcssurc Protection (LTDP)Hinimua RCS vent size, square inches No.of Si pcs capable of injection (PDRVs/vent)

Haxiaam pressurizer level for RCP start, X 0/1 38 1.7 Fuel Handling/Dose Calculations Haxigull reactor coolant gross specific activity Haximm reactor coolant dose equivalent 1.131 Haxinxm secondary coolant dose equivalent I-131 Hinimm reactor coolant boron concentration, ppm Hinimia reactor coolant level Hiniaxm spent fuel pool level Hinimua spent fuel pool boron concentration, ppa Hjnieun spent fuel pool charcoal filter efficiency, X methyl iodine removal Hinfnxsa post accident charcoal filter efficiency, X methyl iodine removal 100/b pCi/gm 1.0 pCi/gm 0.1 pCi/gm 2000 23 ft above flange 23 ft above fuel 300 70 70 TS testing requires 90K cff.TS testing requires 90K eff.COLR 14 Cycle 27, Rev>sion 0 Item g Item/Name Value Remarks: Minimus control room charcoal filter efficiency, X methyl iodine removal Minimus time between reactor criticality and fuel movement, hrs.Source Terms used for dose calculations Dose conversion factors Maximun Gas Decay Tank Xenon-133 concentration, Ci 70 100 ORGEH 2 ICRP-30 100,000 TS testing requires 90X eff.2.0 Main Feedwater (MFII)Feedwater temperature versus load Power Tecyerature 102X 425 F 70X 385 F 30X 322 F DX 100 F 100X design temp is 432 degrees F Feedwater Suction Temperature vs power, nominal Feedwater Suction Pressure vs power, nominal Power 98X 70X 50X 30X Power 98X 70X 50X 30X Temperature 345 F 319 F 295 F 259 F Pressure 277 psig 282 psig 305 psig 370 psig 2.1 3.0 Head-Capacity and HPSH curves Head-Capacity and HPSH curves for main feedwater pcs Main Feedwater pump" Rated Head Main Feedwater purp-Rated Torque Main Feedwater pump-Moment of inertia Elevation of stcam generator inlet nozzle Elevation of main feedwater pump, ft Elevation of condensate pump, ft MFII regulating valve open time on demand, sec MFII regulating vaLve close time on demand, sec MFII regulating valve Cv, full stroke Low Load MFII regulating valve Cv, (bypass valves)MFll Heater resistance (delta p)Auxiliary Feedwater (AFM)Minimus design temperature of the~ater source service water/CST (degrees F)MaxŽ~~design temperature of the water source service water/CST (degrees F)Sec HS&L 2150'89.612 257.75 250.833 10 48.7 see HS&L 0 32(*), 50 80, 100 Selected flow splits are provided for model validation.

Elevation is at center of shaft Assuned value.Actual value-"684.Effective Cv: includes bypass line Design data on the High Pressure Heaters (2 in parallel)is provided Initial AFlJ water source are the CSTs located in the Service Bldg.Safety Related source is the Service'Mater system (lake)." Value different for CHMT integrity.

initial AFIJ water source arc the CSTs located in the Service Bldg.Safety Related source is the Service llater system (Lake).COLR 15 Cycle 27, Revision 0 0 Table 1: UFSAR Chapter 5 Analysj.s Setpoi]Its aTIcL , ut Parameters Item g Item/Name Value Remarks: Startup time for the auxiliary feedwater Imps, sec Hinimm delay for AFM start, sec Haximua delay for AFM start, sec AFM control valve open time on demand, sec AFM controL valve Cv[ftow is f(dP)]TDAFMP, maximm flow, gpm AFM, minimus flows, both generators intact, gpm Hinfmua delay for standby AFM start, min TDAF'M-OI HDAFM-1 HDAFM-47, TOAFM at LO Level both SGs H/A 600 TOAFMP 200/SG HDAFMP 200/SG 10*TOAFM starts on LO levet (17K)in both gens or UV on both unit 4'usses.HDAFM starts on SI (seq), or I.O Level either SG, or trip of both HFP or AHSAC HDAFM acceleration time test results show approximately 1.5 s.For HDAFM, LOOP on sequencer is 47 sec.TDAFM starts at nominal 17'n both SGs HDAFM control valves are normatly open and throttle closed to control , flow between 200-230 gpm NDAFMP valves are 3 Rockwell model¹A4006JKHY stop check valves.TDAFM controL valves (4297, 4298)are 3 Fisher¹470-HS.SBLOCA assunes 200 gpa per SG with the faiture of one DG 4.0 Hain Stem System (HS)Location (and elevation) of condenser dump valves and atmospheric relief valves FulL load steam line pressure drop, psi HS Isolation valve close time[full open to full close]close timei sec HS Isolation valve Cv[f low is f (dp)]CSD.elev 256'.875 ARV-elev 289'.563 approx 45 NSIV-5.0 check vatve-1.0 HSIV-23500 check valve-17580 This estimate, to the governor valves, is provided for comparison purposes only.The check valve is assuned to close in 1 sec under reverse flow.4.1 Hain Stem Code Safety Valves Number of valves (4 per line)Valve flow capacities

-Total, Lbm/hr 6621000 Rated flow (3X accunutation per ASHE,Section III): 1085 psfg o~~~~~~~~~~~~~~~797g700 Lbm/hr (each)1140 psig....~.....~~.....837,600 ibm/hr (each)COLR 16 Cyc1e 27, Revision 0 Item f Item/Name Value Remarks: Valve Flow vs SG pressure (psia), total per bank (4 valves), ibm/sec.1110 1115 1120 1125 1131 1136 1141 1151 1161 1166 1173 1181 1190 1200 1205 1209 1211 0 40 91 141 191 222 223 225 227 228 342 494 646 799 859 920 931 Number of valves in bank Valve sctpoint(s), (first/last three), nominal, psig VaLve blowdown characteristic 4 1085/1140 15X max imm Valves are Crosby AHA-65 6R10 Setpoint tolerance Is+1X/-3X.Nodel valve setpoint at 1.01 (nominal), and fuLL flow at 1.04 (nominaL).

4.2 Atmospheric

relief valves No.Atmospheric relief valves Atmospheric relief valve setpoint/Air-operated, psig Atmospheric relief valve setpoint/Booster, psig Atmospheric relief valve capacity, Lbm/hr 2 1050 During Hot Standby operation setpoint Is lowered to control no load Tavg 1060 313550 at 1060 psig Nax flow is 380000 5.0 5.1 Turbine Generator (TG)Condenser No.of condenser disap valves condenser dms valve open time, sec Condenser dms valve close time, sec Condenser dump valve setpoint(s)

Condenser dump vaLve Cv[flow is f(dP)]For TT: Tavg>555 4 valves,>563 4 valves;no TT: Tref+12 4 valves, Tref+20 4 valves Assusing close time~opening time Gn TT valves control open at 6.7X/F (PID)above 547 with full open sctpoints as described.

On 10X step Load decrease same ratio with a 6F deadband from Tref Oesign Cv (240)from design conditions (302,500 Lbm/hr sat steam at 695 psig)6.0 Chemical and Voltmc Control System (CVCS)CVCS cspsc I ty/pump 3 pmys, 60 gpm msx each Normal ops: 2 charging pumps-onc is manual at 15-20 gpm snd the other in autcmatic.

Charging pumps sre PDPs w/46 gpm total-8 gpm to seals-3 gpm leakage+5 gpm into RCS.40 gpm Letdown COLR 17 Cycle 27, Revision 0 Table 1: UFSAR (-haPter 5 Analysis Setpoints and ut parameters Item 4 Item/Name Value Remarks: CVCS mfnfmua/pm', gpm Type of controLLer (e.g., p+1)and gains 15 PLD 100K,180 sec,10 sec Reactor Hakeup Matei System (QHl)RHll capacf ty/pulp 2 puris, 60 gpa each 7.0 7.1 7.1.1 Emergency Core Cooling System (ECCS)ECCS Delivery's RCS Pressure Residual Heat Removal (RHR)Delivery Hfnfmus RHR Delfvery, train failure vs RCS Pressure Hfnfaxja RHR Delivery, two fxmys runnfng, one line blocked RCS Pressure (psia)155 152 150 140 120 100 80 60 40 20 14.7 RCS Pressure (psfa)155 154 152 150 140 120 100 80 60 40 20 14.7 Delivery (gpm)0 0 0 250 648 836 985 1115 1232 1338 1365 Delivery (gpm)0 0 160 252 516 830 1056 1243 1406 1552 1686 1720 LOCA Appendix K case.Train failure results fn one punp running with 10K degradation with one line bLocked.LOCA Appendix K case (offsfte power availablc).

Two pumps running with 10K degradation with one line blocked.7 1.2 Safety injection (Sf)Delivery vs RCS Prcssure Hfnfmua Si delivery, 2 pumps operating, onc Line spilling Press (psig)1375 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 Delivery (gpm)0.0 62 125 167 201 229 253 273 289 305 321 336 352 368 394 Spill LOCA Appendix K case.Train failure (gpm)results in two punps running wfth 5X 465 degradation with one Line spi llfng to 465 contafcment.

465 465 465 465 465 465 465 465 465 465 465 465 465 COLR 18 Cycle 27, Revision 0 Table 1: UFSAR Chapter 5 Analysis Setpoints and parameters Item 4 Item/Name Value Remarks: Minimun Si delivery, 3 punps operating, non-LOCA Press (psia)Oelivcry (gpm)Loop'A'oop Used for non-LOCA transients, 5X pump degradation Mininnnn Si delivery, 2 pumps operating non-LOCA Maximun Si delivery, 3 punps operating, SGTR 1390 1315 1215 1115 1015 915 815 715 615 515 415 315 215 115 15 Press (psia)1390 1315 1215 1115 1015 915 815 715 615 515 415 315 215 115 15 Press (psig)1375 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 I gl 16 87 147 193 231 266 297 325 352 377 400 423 445 465 485 Delivery Loop'A'gl 8 69 121 162 197 228 255 281 305 328 350 370 390 409 427 Loop A (gpn)76 128 180 221 258'290 320 348 374 398 421 443 464 485 504 19 97 163 214 257 295 329 360 390 418 444 469 493 516 538 (gpn)Loop 8 71 126 169 206 239 269 296 322 346 369 391 412 432 452 Loop 8 (gpm)84 141 198 245 285 321 354 385 413 440 466 490 514 536 558 Used for non-LOCA transients, 5X pump degradation.

The KYPTPE model assunes no pump degradation.

Loop A and 8 pressures are set equal.Used for SGTR.7.3 Ac~lators Munster of accunulators Total volune, each, ft'iquid voluncl ft min/max Liquid volunei ft-Best Estimate initial prcssure, psig-Minimun/Maxlmun 2 1750 1126/1154 1140 700/790 COLR 19 Cycle 27, Revision 0 Table 1: UFSAR Chapter 5 Analysis Setpoints and ut parameters Item 4 Item/Name Value Remarks: initial temperature, F Boron concentration, ppm (mfn/max)105 2100/2600 LBLOCA Hote-Ea analyses use a maximus concentratIon of 3000 ppm 7 4 RMST RUST TeIIperature, min/max, degrees F fffnfmua RWST votIme, gal RMST boron concentration, ppm (min/max)60/80 300,000 2300/2600 Hote-EQ analyses use a maxiImm concentration of 3000 ppm 8.0 Contafrment initial contaf~nt pressure p ia initial containment temperature (LOCA/SLB) degrees F initial relative huaidity, X SM teIIperature min/max, degrees F HaxfImm contafment leakage, wtX/day min-14'max-16.7 90/120 20 30~/80 0.2~HfnfmuII is used for LOCA analysis.Haxfmm is used for the contafwent integrity cases (SI.B).LOCA temperature lower for PCT calculations.

SLB hfgher for contairment integrity*Va tue different for auxiliary feedwater 8.1 ContafImcnt Heat Sinks Listing of Passive Heat Sinks, quantities, metal'fels

~and configurations see HSSL 8.2 Concrete density, conductivity, capacity Bensities, Thermal Conductfvities and Heat Capacities of Heat Sinks Insulatfon density, conductivity, capacity 3.7 ibm/fta 0.0208 BTU/hr F ft 1.11 BTU/ft F 150 ibm/ft 0.81 BTU/hrFf t 31.5 BTU/fthm F note: mfnfImm conductivity corresponds to maximus density, and maxfImm conductivity corresponds to mfnfmun density.Steel density, conductivfty, capacity Stainless steel density, conductfvity, capacfty Contafrment free votune, mfn/max, cu.ft.Ground TNIperature (degrees F)Outside Air Temperature, min/max, degrees F HTC for outside surfaces 490 tbm/ft 28 BTU/hrFft 54.4 BTU/ft F 496 tbm/ft 15 BTU/hrFft 54.6 BTU/fta F 1,000,000/1,066,000 55-10/100 1.65 BTU/hr ft degrees F below grade temperature COLR 20 Cycle 27, Revision 0

'Table 1: UPSAR (-hapter 5 Analysis Setpoints and i put Parameters Item 4 Item/Name Value Remarks: Contairrnent fan cooler performance Contairltent spray flow, min/max, each, gpm Tenp Hin Hax (deg F)(X106BTU/hr) 120 2.05 4 F 55 220 35.1 99.2 240 40.8 113.8 260 46.8 129.3 280 52.9 145.5 286 54.7 150.4 1300/1800 8.3 Oclays for CRFCs and Spray punps CRFC delay, offsite power available, seconds CRFC delay, offsite power not avaf lable, seconds Contafnment Spray, 1300 gpm each fxlp, maxfmun delay, sec Contafreent Spray, 1800 gpm each punp, mfnfmun dele/, sec ContafrInent Oesfgn pressure, psig Ofstance Basement floor to Springline, feet Oistance Sprfngline to top of done, feet 34 44 28.5-onc punp 26.8-two pumps 9/(14 w LoOP)60 95 52.5 includes 2.0 sec SI delay includes 2.0 sec SI delay This delay is from the tfme Containment Hi-Mi setpoint is reached.It includes instrunent delay and spray line fill time.This delay is from the tfme of break.8.4 Contairwent Surp Hinimun wtX of HaOH Tank 30 9.0 Control Systems (Reactor, FM, przr Level, Turbine, AFIJ)Tavg versus power pressurizer pressure and level algorithms SO secondary level algorithm H/A N/A H/A Tavg ramps Linearly from 547 degrees F at OX power to 561 degrees F at 100K power pressurizer pressure setpoint is constant at 2235 psig.Pressurizer leveL reaps from 35K to 50K for 0 to 100K power (547-561 degrees F).Level remains constant at 52X to 100X power.(Power from turbine 1st stage press.)10.0 10.'I 10~1.1 Sa fcty System Setpoints Reactor Protection System power range high neutron flux, high setting nominal accident analysis delay time, sec 1.18 0.5 1.09 10.1.2 Power range high neutron flux, Low setting nominal accident analysis 0.250 0.350 COLR 21 Cyc1e 27, Revision 0 Xtem 4 Item/Name Value Remarks: delay time, sec 0'10.1.3 Overtemperature delta T nominal accident analysis delay time, sec Variable Variable 6.0 Total delay time-from the time the tenperature difference in the coolant Loops exceeds the trip.setpoint until the rods are free to fall 10.1A Overpower delta T nominal accident analysis delay time, sec Variable Variable 2.0 Hot explicitly modelled in safety analysis 10.1.5 High pressurizer pressure nominal, psig accident analysis, psia delay time, sec 2410 2.0 10.1.6 Low pressurizer pressure nominal, psig accident analysis, psia delay time, sec 1873 1775 (non-LOCA) 1715 (LOCA)1905 (SGTR)2.0 10.1.7 Low reactor coolant flow nominal accident analysis delay time, sec 91K of normal indicated flow 87X per Loop 1.0 10.1.8 Low-Low SG level nominal accident analysis delay time, sec 17K of the narrow range Level span OX of narrow range Level span 2.0 While trip setpoint could be as Low as 16K, AFll initiation Limits to 17K 10.1.9 Turbine Trip (low fluid oil pressure)nominal, psig accident analysis delay time, sec 45 H/A 2.0 Hot explicitly modeled in safety analysis COLR 22 Cycle 27, Revision, 0

~.~Table 1-UPSAR Chapter 15 Analysis Setpoints and Input parameters Item g Item/Name Value Remarks: 10.1.10 Undervoltage ncminal, V accident analysis delay time.sec 3150 1~5 Safety analysis assunes RCCAs are released 1.5 scc.after sctpoint is released.10.1.11 Undcrfrcqumcy nominal, Hz accident analysis delay time 57.7 57.0 1.2 Analysis is performed but not explicitly modeled in safety analysis.Safety analysis assunes RCCAs are released 1'sec after setpoint is reached.10.1.12 Intermediate range nominal, RTP safety analysis, RTP delay time, sec 0.25 H/A H/A Hay fluctuate duc to core flux Hot explicitly modeled in safety'nalysis 10.1.13 Source Range nominal, cps accident analysis, cps delay time, sec 1.4E+5 1 AL OE+5 2.0 Highest nominal value 10.1.14 High Pressurizer level nominal accident analysis delay time, sec 0.90 0.938 2.0 10.2 10.2.1 10.2.1.1 Englneercd Safety Features Actuation System Sa fcty injection System'High con'tailNcAt prcssure Hominal setpoint, psig Accident Analysis setpoint, psig oelay time, sec 4.0 6.0*34 44 w/LOOP*only modeled in accident analysis for start of containment fan coolers.Time delays are for start of containment fan coolers.10.2.1.2 Lou pressurizer pressure Hominal setpoint, psig 1750 COLR 23 Cycle 27, Revision 0

~..~Table 1: UFSAR Chapter 15 Analysis Setpoints and input parameters Xtem 4 Xtem/Name Value Remarks: Accident Analysis setpoint, psia Delay time, sec 1785, SGTR 1730, non-LOCA 1715, LOCA 2.0 10 2.1 3 Low ate~line pressul e Hominal setpolnt, psig Accident Analysis setpoint, psig Delay time, sec 514 372.7 2.0 See HS&L See NS&L 10.2.2 Contairwmt Spray Hominal Setpoint, psig Accident analysis setpoint, psig Delay time, sec 28 32.5 28.5 Sec HS&L Delay time includes time to fill lines.See HS&L 10.2.3 AFM System Lcw low ate~generator water Nominal Setpoint Accident analysis setpoint Delay time, sec 17 X of narrow range instrunent span each steam generator 0 X of narrow range instrunent span each steam generator 2.0 A positive 11K error has been included to account for the SG level measurement system at a contairraent tecperature of 286 F 10.2 4 10.2.4.1 Steam Line Isolation High conte irsaent pressure Nominal Setpoint, psig Accident analysis setpoint Delay time 18 H/A H/A Not explicitly modeled Not explicitly modeled 10.2 4.2 High stem flow, coincident with low Tavg and SI Hominal Sctpoint Accident analysis setpoint Delay time 0.4E6 lb/hr equivalent steam flow at 755 psig and Tavg<545 F N/A N/A Note flow setpoint is below nominal full power flow and therefore this portion of logic is made up at power Not explicitly modeled Hot explicitly modeled.Steam line isolation is assumed concurrent with SI (i.e.2 s delay+'5 s valve stroke)10.2.4.3 High-high stem flow, coincident SI Hominal Setpoint Accident analysis setpoint 3.6E6 lb/hr equivalent steam flow at 755 psig N/A Hot explic>tly modeled COLR 24 Cycle 27, Revision 0 Item f Item/Name Value Remarks: Delay time H/A Hot explicitly modeled.Steam Line isolation is assumed concurrent with si (i.e.2 s delay+5 s valve stroke)10.2.5 Feedwater isolation 10.2.5.1 High stem generator water level 11 0 Hominal Setpoint Accident analysis setpoint Delay time Bill Stem Generators Heat load per SG, BTU/hr Primary flow per SG, Klb/hr Steam flow per SG, Lb/hr (clean, unplugged)

Secondary design pressure, psig Secondary design teaperature, F Maxicxla moisture carryover, X Harrow range level tap locations, inches above TS secondary face Mide range level tap Locat'ions, inches above TS secondary face 85X of the narrow range instrunent span each SG 100X of the narrow range instrunent span each SG 2.0 2,602,000,000 PluggingX Flow Klb/hr 0 34950 5 34630 10 34280 15 33850 3,264,358 at 877 psia 1085 556 0.10 386/s/529/I 8/~/529/e Lnstrunent loop only Design flows at T,,~573.5 F conditions for T~~573.5 F SG Pressure Drops Secondary nozzle to nozzle dP Q full power, psi Secondary nozzle to nozzle dP Q full po~er, psi primary nozzle to nozzle unrecoverable pressure cirop vs.plugging, psi 14.7 7.5 PluggingX ap psi 0 31.01 5 33.27 10 35.82 15 38.72 Value is totaL static pressure drop.Pressure drop from top of U-bend to outlet.See associated flows for X plugging.11.2 SG Tubes Ho.of tubes per SG Tube 00, inches Tube average wall thickness inches Maxinxla tube length, ft Minimus tube length, ft Average length, ft 4765 0.750 0.043 70.200 55.925 61.988 Includes length in tubesheet (2x25.625")

includes length in tubesheet (2x25.625")

includes length in tubesheet (2x25.625")

COLR 25 Cycle 27, Revision 0 I Table 1: UFSAR (-'hap<<r 5 Analysis Setpoints and ut parameters Item 4 Item/Name Value Remarks: Hlnfaae U-bend radius, inches Haxiaam U-bend radius, inches U-bend radius of shortest tube(s), inches Average U-bend radius, inches Tube straight Length (one side)above secondary face, inches (min/max/average)

Secondary heat transfer area, ft per SG Primary heat transfer area, ft~per SG overall bundle height, ft above secondary face of TS 3.979 54.007 4.044 24.51 303/lg/310/i/308.182 54,001 47,809 30.427 Note: this is not the bend radius for the shortest tube.Tube material SG Tube Haterial Thermal Conductivity, BTU-in/hr-ft'-F SG Tube Haterial Specific Neat BTU/lb.F SB-163 Temp F 200 300 400 500 600 Temp F 200 300 400 500 600 Alloy N06690 Conductivity 93 100 107 114.5 122 Conductivity 0.112 0.1155 0.119 0.1225 0.126 Distance from top of tube bundle to 33'RL, ft 5.703 11.3 11.3.1 SG Voltmes SG Secondary Side Vol~secondary volte, ft (total)Secondary volune up to lower NRL tap, ft Secondary volune up to upper NRL tap, ft 4512.7 1893.2 3460.4 11.3.2 Riser Volmes Secondary side bundle volune (TS to top of U-bend inside shroud), fthm secondary riser volune, top of U-bend to spill-over point, ft'281.8 507.0 Equivalent to LOFTRAN riser volune.11.3.3 Dosncomer Vol mes Downcomer volune, top of TS to top of U-b&, ft'owncomer volunc, top of U b Qf to spi point, ft'59.6 1437.3 11.3.4 SG Primary Side Valuate Inlet plenua per SG, fts Outlet plenun per SG, fthm 129.65 129.65 COLR 26 Cycle 27, Revision 0 Table 1: UPSAR Chapter 15 Analysis Setpoints and Input Parameters Xtem f Xtem/Name Value Remarks: Tube primary velum per SG, fta Primary total volune per SG, fthm Circulation ratio (100X power, clean, unplugged)

Tubesheet thickness, inches 710.3 969.6 5.39 25.625 Circulation ratio=bundle flow g steam flow.Assunes 40,000 Lbmghr b lowdown.Includes cladding.11.4 SG Primry Side Dimensions PHmary head radius, inches Divider plate thickness, inches Inlet and outlet nozzle, inside diametel cylindrical section, inches Nozzle divergence angle, degrees Nozzle inside diameter at plena, inches Nozzle Lengths, inches Heigth from SG primary head bottom (outside)to top of Ts, inches Distance tube sheet primary face to hot leg centerline, ft.58.375 1.875 31.200 11 30'7.0 cylindrical section conical section total length 90'lle 6.654 8.75 13.0 21.75 Radius to clad surface.11.5 SG Secondary Side Dimensions Lower shell inside diameter, inches Lower shell thickness, inches Tube shroud inside diameter, inches Distance top of tube bundle to top of steam nozzle, inches steam nozzle flow restricter area, ft'istance secondary face of TS to centerline of feedwater nozzle, inches Distance secondary face of TS to centerline of feed ring, inches Cross-sectional area of tube bundle ft~Distance top of tube bundle to spill-over point, inches Primary side roughness, micro-inches 122 2.875 114 298.5 1.4 407'i, 374 41.64 178.0 Hozzles, head 60 Tubes 60 This value is total area inside shroud.This value is equivalent to the riser height for the DSG.values given are conservative assunptions.

SG Secondary Side Mater Hasses Secondary~ater inventory, 100)', power, T,,~573.5, no plugging, ibm Secondary water inventory, 100'ower, T, 559, no plugging, Lbn 86,259 liquid 5,286 steam 85,547 liquid 4,675 steam gest estimate value.gest estimate value.11.7 SG Primary Side Head Loss Coefficients COLR 27 Cycle 27, Revision 0 Item 4 Item/Name Value Remarks: gG inlet nozzle/plenum loss coefficient, ft/gpm gG outlet nozzle/plenum loss coefficient, ft/gpm gG tubing loss coefficient, ft/gpm SG Cubing loss coefficient, sCraight section (in), ft/gpm'G tubing loss coefficient, U-bend section, ft/gpm$0 tubing Loss coefficient, straight section (out), ft/gpm 1.01E-09 for ID<<31.2<<3.31E-10 for IO<<31.2<<9.62E-09 for OX plugging 1.32E-08 for 15X plugging 4.19E-09 for OX plugging 5.73E-09 for 15K plugging 1.02E-09 for OX plugging 1.40E-09 for 15K plugging 4.41E.09 for OX plugging 6.08E-09 for 15X plugging For cube ID<<0.664", Ao>><<11.458 f C2~A~~>>assumed to be uniform.For tube ID<<0.664<<, A<<11.458 ft, A,~>>"-9.739 ft.Plugging is assuned to be uniform.For tube 10=0.664", Ao>>=11.458 fc', A=9.739 ft.Plugging is assumed to be uniform.For tube ID=0.664"~Ao"-11.458 fthm, Al5>>=9.739 ft2.Plugging is assumed to be uniform.COLR 28 Cycle 27, Revision 0 4

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