ML17265A630
| ML17265A630 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/18/1999 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17265A628 | List: |
| References | |
| NUDOCS 9904290042 | |
| Download: ML17265A630 (35) | |
Text
GINNA STATION COLR Cycle 28 Revision t CORE OPERATING LIIVIITS REPORT (COL R)Re ponsible Hanaget H/I E/9 9'ffective Date Controlled Copy No.(9q04290042 990419 PDR ADOCK 05000244i P PDRI I 0
R.E.Ginna Nuclear Power Plant Core Operating Limits Report Cycle 28 Revision 1 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 (Fo(Z))2.6 Nuclear Enthalpy Rise Hot Channel Factor (F"~2.7 AXIAL FLUX DIFFERENCE
.2.8 RCS Pressure, Temperature, and Flow Departure Boiling (DNB)Limits 2.9 Boron Concentration
.~~~)~~~~~~~from Nucleate~~~~~3 3 3 3 4 4 4 5 5 3.0 UFSAR CHAPTER 15 ANALYSIS SETPOINTS AND INPUT PARAMETERS
.....5
4.0 REFERENCES
6 FIGURE 1-REQUIRED SHUTDOWN MARGIN....................7 FIGURE 2-CONTROL BANK INSERTION LIMITS................
8 FIGURE 3-K(Z)-NORMALIZED Fo(Z)AS A FUNCTION OF CORE HEIGHT.....
9 FIGURE 4-AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AND TARGET BAND LIMITS-AS A FUNCTION OF RATED THERMAL POWER TABLE 1-UFSAR CHAPTER 15 ANALYSIS SETPOINTS AND INPUT PARAMETERS.
10 11 COLR Cycle 28Revision 1 R.E.Ginna Nuclear Power Plant Core Operating Limits Report Cycle 28 Revision 1=1.0 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 28, Revision 1 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)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 (non main feedwater operation).
2.1.2 2.1.3 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 and the status of the main feedwater system.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 above 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 defined as z 221 steps.COLR Cycle 28, Revision 1 2.4 Control Bank Insertion Limits (LCO 3.1.6)(Limits generated using Reference 1)2.4.1 2.4.2 The control banks shall be limited in physical insertion as shown in Figure 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)F (Z)s~F/*K(Z)P Fo(Z)~QFog*K(Z)0.5 when P>0.5 when P s 0.5 where: 2 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" (LCO 3.2.2)(Limits generated using Reference 1)2.6.1 F"~s F"~*(1+PF~*(1-P))where: PF~-0.3, and THERMAL POWER'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 28, Revision 1 0
3 2.8 RCS Pressure Tem erature and Flow De arture from Nucleate Boilin~DNB Li it LLBB 3.4.13 (Limits generated using Reference 4)2.8.1 2.8.2 2.8.3 The pressurizer pressure shall be>2205 psig.The RCS average temperature shall be s 577.5 F.The RCS total flow rate shall be a 177,300 gpm (includes 4%minimum flow uncertainty per Revised Thermal Design Hethodology).
2.9 Boron Concentration (LCO 3.9.1)(Limits generated using Reference 1)2.9.1 The boron concentrations of the hydraulically coupled Reactor Coolant System, the refueling canal, and the refueling cavity shall be)2300 ypm.3.0 UFSAR CHAPTER 15 ANALYSIS SETPOINTS AND INPUT PARAHETERS 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 28, Revision 1
4.0 REFERENCES
1.WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, Quly 1985.2.WCAP-10054-P-A and WCAP-10081-A,"Westinghouse Small Break ECCS Evaluation Model Using the NOTRUHP Code," August 1985.WCAP-10924-P-A, Volume 1, Revision 1,"Westinghouse Large-Break LOCA Best-Estimate Methodology, Volume 1: Model Description and Validation Responses to NRC Questions," and Addenda 1,2,3, December 1988.WCAP-10924-P-A, Volume 2, Revision 2,"Westinghouse Large-Break LOCA Best-Estimate Methodology, Volume 2: Application to Two-Loop PWRs Equipped with Upper Plenum Injection," and Addendum 1, December 1988.WCAP-10924-P-A, Volume 1, Revision 1, Addendum 4,"Westinghouse Large-Break LOCA Best-Estimate Hethodology, Volume 1: Model Description and Validation, Addendum 4: Model Revisions," March 1991.WCAP-13677-P-A,"10 CFR 50.46 Evaluation Model Report: WCOBRA/TRAC Two-Loop Upper Plenum Injection Model Updates to Support ZIRLOŽCladding Option," February 1994.WCAP-12610-P-A,"VANTAGE+Fuel Assembly Reference Core Report," April 1995.WCAP-8385,"Power Distribution Control and Load Following Procedures-Topical Report," September 1974.4.WCAP-11397-P-A,"Revised Thermal Design Procedure", April 1989.COLR Cycle 28, Revision 1
2.5 ACCEPTABLE
OPERATION~~(0.2 45)(0.2 40)O MO b D Q LLJ rL z P-D x (o 1.5 (1500.1,45)
I I 1 (1500,1,00)
I 0.5 UNACCEPTABLE OPERATION (0,1,80)0 1500 ANTE: 1000 500 COOLANT BORON CONCENTRATION (ppm)D I DDT<<I\D<<~MTW-T I TDD~MTW Two Loop Operation-non MFW means that the main feedwater system is not supplying the steam generators Two Loop Operation-MFW means that the main feedwater system is supplying the steam generators FIGURE I RE(UIRED SHUTDOWN MARGIN COLR Cycle 28, Revision I CL I (0 O~~V)O CL 6$~CL 220 200 1 80 (0,164 160 140 120 100 80 60 (0, 53)40 20 B Bank 1em.')(30.C Bank 66.6,'B ank (tel.$64)0 10 20 30 40 50 60 70 80 90 100 Core Power (Percent of 1520 MWT)*The fully withdrawn position is defined as a 221 steps.FIGURE 2 CONTROL BANK INSERTION LIMITS COLR Cycle 28, Revision 1
1.2 N+1.0 pP 0.8 Ul C C$I 06 Q.C~~X 0.4 QP N~~lg 202 0 R Total Fo=2.450 E~ft~K 0.0 1.0 11.783 1.0 0,0 0.0 2.0 4.0 6.0 8.0 Elevation (ft)10.0 11.783 FIGURE 3 K(Z)NORMALIZED Fq(Z)AS A FUNCTION OF CORE HEIGHT COLR Cycle 28, Revision I
(.11,90)00 NOT OPERATE IN THIS AREA WITH AFD OUTSIOE THE TARGET BAt4)(11/0)80~O a Q 60 Q.ACCEPTABl.E OP ERAT)ON WlTH AFD"--'--""'UTSDE THE'AROET BAND WlTH<<1 t%PENALTY DEVIATlON THE (41,60)(31,60)40 x a I~ACCEPTABLE
.OP ERAT)ON 20-30-20-10 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 Cycle 28, Revision I Tah3.e 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters em 4 Item/Name Value Remarks: 1.0 Reactor Coolant System (RCS)Upper head volune, ft Upper PL'enure volune, fts Top of fuel volte, ft Inlet nozzle(s)volma, total of two, ft Outlet nozzle(s)volune, total of two, ft Active fuel volume, ft Bottom of fuel volune, ft Lover PLefwn volte, ft Downcomer volune, above bottom of cold leg, ft Downcomer, lo~er core plate to elevation of the bottom of the cold Leg volune, ft'arrel baffle, lower core plate to upper core plate volte, ft'otal volte, fthm Hot leg pipe volune per loop volune, fto Cold leg volune per loop+cross over, fts RC purp volune per pm@, ft Cold Leg pipe ID, in./Pwp suction ID, in.Hot Leg pipe IO, in.Design pressure, psig Design temperature, F Cold Leg and Hot Leg 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 650 246'0" 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 bottcm of upper core plate, inside barrel baffle.Includes nozzle forging protrusion into vessel.Does not include mating hole in barrel, this is included in the Upper PLenua 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 bottcm of cold leg elevation tc bottom of upper support plate Top of lower core plate to elevation of bottom of cold leg Top of lower core plate to bottcm of upper core plate.Includes nozzl es Reactor Coolant Puap Head-Capacity and NPSH curves for reactor coolant pNps/Homologous Curves Rated RC pap head and flow, ft&gpll Rated RC pump torque and efficiency Q rated head/flow, ft-lb, fraction RCP Pmp Rated Power (hot, 556 degrees F)RCP Hotpr Rated Speed, RPH Homent of inertia of punp and motor, Lb-ft'C pump heat, HQt (max/min per pap)See Engineering 252;90,000 84K efficiency at hot condi t I ons 4842 BHP 1189 80,000 5, 4 Homologous Curves are available in RETRAH Pwp power varies with RCS temp from approx 4 Wt to 5 H'Mt 1.2 Core COLR Cycle 28, Revision 1 Tab3.e 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters em 4 Item/Name Value Remarks: Rated power, HMt Reactor power tncertainty, X RTP Bypass, X Upper head bypass, X Upper head tenyerature, degrees F Heat transfer area, ft 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 assenhly 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, lbn Hass of clad, ibm Hunber of fuel pins per fuel assenhty (FA)Ho.of Fuel Assemblies Fuel pin pitch, in.Bottom nozzle weight and volune Top nozzle, w/insert, weight and volune Fuel Assembly resistance
[core dP f(flow)],,psi f(lb/hr)Fuel Assenhly free flow area, in 105,500 25,927 179 121 0.556 9.1 lbs.31.5 in 18.15 lbs.62.9 inn core delta P~20 psi Q flow~170,200 gpn 34.75 Thimble plugs removed.Single assembly.1.3.3 Fuel pin geometry Pellet diameter, in.Clad OD/ID, in./in.0.3444 0.400/0.3514 1.3.4 Control Rod C Tnstnmat Guide T~Ho.of control rod guide tubes Ho.of instrunent guide tubes Control Rod Guide tube upper part (X)/ID, in./in.instrunent Guide tube OD/1D, in./in.Guide tube lower part OD/1D, in./in.Control Rod Drop Times, maxinuns, sec.Control rod maxinun withdrawal rate, in./min.16 0.49/0.528 0.395/0.350 0.4445/0.4825 Kon-LOCA 2.4 LOCA 3.0 45 Allowances are added to the Tech Spec allowable value.COLR 12 Cyc1e 28, Revision 1 Table 1: UPSAR Chapter 15 Analysis Setpoints and Input parameters em j Item/Name Value Remarks: Control rod maxiaxsa insertion rate, pcm/sec.Control rod insertion limits Hot charnel radial peaking factor Heat Flux Hot channel factor FQ 90 See COLR 1.75 2.45 1.4 Pressurizer Code safety valve flow capacity, ibm/hr Code safety valve open time Code safety valve setpoint Spray valve Spray valve Spray valve Spray valve PORV nunber flow capacity, gpa/valve setpoint-start open/full open time constant, sec~PORV f low capacity, ibm/hr PORV Cv PORV open time PORV close time Backup Heaters Hiniaasn heater capacity required for LOOP, kM Heater bank controller type PORV setpoint[normal)open/close, psig PORV setpoint (LTOP)open/close, psig PORV blowdown characteristic Hester capacity w/bank capacity and setpoints, kM Control banks 288,000 0.8 sec seal clearing time 2485 psig 2 200 2260/2310 5 2 179,000 50 gpm/(paid)1/2 1.65 sec+transmitter 3.95 sec+transmitter 2335/2315 430 800 0 kM at 2250 psig and 400 kM at 2220 psig Full on at 2210 psig and resets at 2220 psig 100 proportional 400 kM Rating at 2485 psig plus 3X accuml at i on Crosby Hodel HB-BP-86, size 4K26 Tolerance is+2.4X/-3X.Proportional Assumed value Steam flow at 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 E11GH.HSAE1, with a time response of 1 sec (time to 90X of final value for step input)LTOPs transmitter is Foxboro E11GH-HSAE1, with a time response of 1 sec (time to 90X of final value for step input)1.4.1 Pressurizer vol~(s)(100X/OX power)Mater, ft'100X/OX power)Steam, ft (100X/OX power)Total, fts Pressurizer iD, ft-in 396/199 404/601 800 83.624 in/cladding thickness is 0.188 in COLR 13 Cycle 28, Revision 1 Table 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters em 4 Item/Name Value Remarks: Surge line LD, in.Spray line 10, in.Surge line volume, fthm'8.75 3.062 18.4 Surge line is 10 in schedule 140 1.4.2 Pressw izer Level Lower level tap elevation Upper Level tap elevation Pressurizer level vs X power Distance Hot Leg Centerline to Lower Tap, ft Haxiaxm level allowed for steam bubble, X 257'275'Xpower Level 0 X 35X 100 X 50X 10.750 87 Pressurizer level is ramped linearly between these points.Hot used in Chapter 15 analyses.1.5 RCS FLows, Tcaperature and Pressures Total reactor coolant flow, gpm (15X plugging)Total reactor coolant flow, gpn (15X plugging)Average reactor coolant teeperature, degrees F (Full power/HZP)
Reactor coolant pressure, psig Reactor coolant flow mcertainty, X nominal Reactor coolant tetperature certainty, degrees F Reactor coolant pressure mcertainty, psi DNB Limit (safety analysis limit)170,200 177,300 559 to 573.5/547 2235 s 30 1.40 Use for non DNB Use for statistical DHB Cycle 28 T ,-" 561 1.6 Low Temperature Overpressure Protection (LTOP)Hiniaam RCS vent size, square inches~No.of SI ixsrps capable of injection (PORVs/vent)
Haxinam pressurizer level for RCP start, X 0/1 38 1.7 Fuel Handling/Dose Calculaticns Haxitmm reactor coolant gross specific activity Haxinxm reactor coolant dose equivalent i-131 Haxitmm secondary coolant dose equivalent I-131 kininam reactor coolant boron concentration, ppm Hinilmm reactor coolant Level Hinicxm spent fuel pool Level Hlnlaxm spent fuel pool boron concentration, ppm Hinislm spent fuel pool charcoal filter efficiency, X methyl iodine removaL Hiniaxm post accident charcoal filter efficiency, X methyl iodine removal 100/t 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 90X eff.TS testing requires 90X eff.COLR 14 Cycle 28, Revision 1
.Table 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters em 4 Item/Name Value Remarks: Hinisua control rocm charcoal filter efficiency, X methyl iodine removal HInisass time between reactor criticality and fuel movement, hrs.Source Terse used for dose calculations Dose conversion factors Haxisxza Gas Decay Tank Xenon.133 concentration, Ci 70 100 ORGEN 2 ICRP-30 100,000 TS testing requires 90X eff.2.0 Hain Feedwater (HFM)Feedwater tesperature versus load Power Teeperature 102X 425 F 70X 385 F 30X 322 F OX 100 F 100X design teffp is 432 degrees F Feedwater Suction Temperature vs Power, nominal Feedwater Suction Pressure vs Po~er, nominal Power 98X 70X 50X 30X Power 98X 70X SOX 30X Temperature 345 F 319 F 295 F 259 F Pressure 277 psig 282 psig 305 psig 370 psig 3.0 Head-Capacity and NPSN curves Head-Capacity and NPSN curves for main feedwater Fxmps Hain Feedwater Ixgp-Rated Head Hain Feedwater pmp-Rated Torque Hain Feedwater punp~Homent of Inertia Elevation of steam generator inlet nozzle Elevation of main feedwater pump, ft Elevation of condensate punp, ft HFM regulating valve open time on demand, sec HFM regulating valve close time on demand, sec HFll regulating valve Cv, full stroke Low load HFll regulating valve Cv, (bypass valves)HFM Neater resistance (delta P)Auxiliary Feedwater (AFM)Hinieasn design temperature of the water source service~ster/CST (degrees F)Haxisxsa design tecperature of the water source service water/CST (degrees F)See Engineering 2150'89.612 257.75 250.833 10 725 l8.7 see Engineering 30, 32 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 Nigh Pressure Heaters (2 in parallel)is provided Initial AFM~ster source are the CSTs located in the Service Bldg.Safety Related source is the Service Mater system (I eke).Initial AFM water source are the CSTs located in the Service Bldg.Safety Related source is the Service Mater system (lake).COLR 15 Cycle 28, Revision 1
Tab9.e 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters em g Item/Name Value Remarks: Startup time for the auxiliary feedwater@cps, SCC HiniImNI delay for AFM start, sec HaxiImsn delay for AFM start, sec AFM control valve open time on demand, sec AFM control valve Cv[f low is f(dP))TDAFMP, maxiImsn flow, gpm AFM, minirmIII flows, both generators intact, gpm HiniImmI delay for standby AFM start, min TDAFM.0, HDAFM 1 H/A 600 TOAFMP 200/SG HDAFMP 200/SG 10~TDAFM starts on LO level (17K)in both gens or IN on both unit 4Kv busses.HDAFM starts on SI (seq), or LO level either SG, or trip of both HFP or AHSAC NOAFM acceleration time test results show approximately 1.5 s.Increased time of 600 sec.will be used in future analysis HDAFM control valves are normally open and throttle closed to control flow between 200'30 gpm HDAFMP valves are 3 Rockwell model¹A4006JKHY stop check valves.TDAFM control valves (4297, 4298)are 3 Fisher¹470-HS.SBLOCA assunes 200 gpn per SG with the fai lure of one OG 4.0 Nein Stem System (NS)Location (and elevation) of condenser ckmp valves and atmosphcl"Ic I'clicf valves Full load steam line pressure drop, psi HS Isolation valve close time[full open to full close)close.time, sec NS Isolation valve Cv[flow is f(dP))CSO.elev 256'.875 ARV-elev 289'.563 approx 45 HSIV-5.0 check valve-1.0 HSIV-23500 check valve.17580 This estimate, to the governor valves, is provided for comparison purposes only.The check valve is asswIed to close in 1 sec under reverse flow.4.1 Nain Stam Code Safety Valves HImher of valves (4 per line)Valve flow capacities
-Total, ibm/hr 6621000 Rated flow (3X accImalation per ASHE,Section III): 1085 psig................
797,700 lbn/hr (each)1140 psig..~..............
837,600 Ibm/hr (each)COLR 16 Cycle 28, Revision 1
~Table 1: UPSAR Chapter 15 Analysi:s Setpoints and Input Parameters em 4 Item/Name Value Remarks: Valve Floe vs SG pressure (psia), total per bank (4 valves), ibm/sec.Nunber of valves in bank 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 Valve setpoint(s), (first/last three), nominal, psig Valve bloudo1a1 characteristic 1085/1140 15X max 1 SMS Valves are.Crosby¹HA-65 6R10 Setpoint tolerance is+1X/-3X.Nodel valve setpoint at 1.01 (nominal), and full flo11 at 1.04 (nominal).
Atmospheric relief valves No.Atmospheric relief valves Atmospheric relief valve setpoint/Air-operated, ps 1 9 Atmospheric reLief valve setpoint/Booster, psig Atmospheric relief valve capacity, Lbn/hr 1050 1060 During Hot Standby operation setpoint is Lowered to control no load Tavg 313550 at 1060 psig Nax floM is 380000 5.0 Turbine Generator (TG)5.1 Condenser No.of condenser du1p valves Condenser d1S1p valve open time, sec Condenser cklp valve close time, sec Condenser cANp valve setpoint(s)
Condenser dip valve Cv[floe is f(dP))for TT: Tavg>555 4 valves,>563 4 valves;no TT: Tref+12 4 valves, Tref+20 4 valves ASS1N1ing close time=opening time On TT valves control open at 6.7X/F (PID)above 547 111th full open setpoints as described.
On 10X step load decrease same ratio with a 6F deadband from Tref Design Cv (240)from design conditions (302,500 ibm/hr sat steam at 695 psig)6.0 Chemicat and Vol~Control System (CVCS)CVCS capac1 ty/pump 3 pcs, 60 gpn max each Normal ops: 2 charging punps-one is manual at 15-20 gpn and the other in automatic.
Charging pcs are PDPs w/46 gpm total-8 gp11 to seals-3 gpm Leakage+5 gp11 into RCS.40 gpm Letdo1a1 COLR 17 Cycle 28, Revision 1 Tahie 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters
\Item/Name Value Remarks: CVCS minimtsa/IxN0P, 9Pm Type of controller (e.g., P+I)and gains 15 PID 100X,180 sec,10 sec 6.1 Reactor Nak~Mater System (RW)RNM capac I ty/pep 2 Ixmps, 60 gpm each 7.0 7.1 7.1.1 Emergency Core Cooling System (ECCS)ECCS Delivery vs RCS Pressure Residual Heat Removal (RHR)Delivery vs RCS Pressure Ninisass RHR Delivery, train failure Nininasa RHR Delivery, two Ixmps ruwing, one line blocked RCS Pressure (psia)155 152 150 140 120 100 80 60 40 20 14.7 RCS Pressure (psia)155 154 152 150 140 120 100 80 60 40 20 14.7 Delivery (gpm)0 0 0 250 648&36 985 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 in one pup running with 10X degradation with one line blocked.LOCA Appendix K case (offsite po~er available).
Two pcs running with 10X degradation with one line blocked.7.1.2 Safety Injection (Sl)Delivery vs RCS Pressure Nininua SI delivery, 2 Ixmps operating, one line spilling Press (psig)1375 1300 1200 1100 1000 900 800 700.600 500 400 300 200 100 0 Delivery (gpn)0.0 62 125 167 201 229 253 273 289 305 321 336 352 368 384 Spill LOCA Appendix K case.Train failure (gpm)results in two Ixmps running with SX 465 degradation with one line spilling to 465 contaireent.
465 465 465 465 465 465 465 465 465 465 465 465 465 COLR 18 Cycle 28, Revision 1 Table 1:.UFSAR Chapter 15 Analysis Setpoints and Input Parameters em 4 Item/Name Value Remarks: Hinisxsa Sl delivery, 3 purps operating, non-LOCA Hinisxsa Si delivery, 2 pwys operating non-LOCA Press (psia)1390 1315 1215 1115 1015 915 815 715 615 515 415 315 215 115 15 Press (psia)1390 1315 1215 1115 1015 915 81$715 615 515 415 315 215 115 15 Delivery Loop'A'BI 16 87 147 193 231 266 297 325 352 377 400 423 445 465 485 Delivery Loop'A'BI 8 69 121 162 197 228 255 281 305 328 350 37D 390 409 427 (gpm)Loop 19 97 163 214 257 295 329 360 390 418 444 469 493 516 538 (gpm)Loop 8 71 126 169 206 239 269 296 322 346 369 391 412 432 452 Used for non-LOCA transients, SX pump degradation Used for non.LOCA transients, 5X punp degradation.
Hex(asm Si delivery, 3 pcs operating, SGTR Press (psig)1375 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 Loop A (gpn)76 128 180 221 258 290 320 348 374 398 421 443 464 485 504 Loop B (gpm)84 141 198 245 285 321 354 385 413 440 466 490 514 536 558 The KYPIPE model asswes no pm'egradation.
Loop A and B pressures are set equal.Used for SGTR.7.3 Acnmslators Nwker of accumulators Total volune, each, fts Liquid volune, fts-min/max Liquid volune, ft'Best Estimate initial pressure, psig-Hinisxla/Haxinua 2 1750 1111/1139 1140 700/790 COLR 19 Cycle 28., Revision I Tah9.e 1: UPSAR Chapter 15 Analysis Setpoints and Input Parameters Item/Name Value Remarks: initial te<<perature, F Boron concentration, ppm (min/max)105 2100/2600 LBLOCA Hote.EQ analyses use a maxi<<un concentration of 3000 ppn 7A RMST RMST Te<<perature, min/max, degrees F Ninitmsn RMST volw>>, gal RMST boron concentration, ppm (min/max)60/80 300,000 2300/2600 Upper limit increased to 104 Note-EQ analyses use a maxinxin concentration of 3000 ppn 8.0 Conte i~t initial contairment pressure, psia initial contaim>>nt te<<perature (LOCA/SLB) degrees F initial relative hunidity, X SM temperature min/max, degrees F Haxitmln contaim>>nt leakage, wtX/day min-14.5 max-15.7 90/120~'0 30/$5 0.2 lfinitmjn is used for LOCA analysis.Haxi<<xsn is used for the containment integrity cases (SLB).LOCA te<<perature lower for PCT calculations.
SLB higher for contaim>>nt integrity" Contairment Heat Sinks Listing of Passive Heat Sinks, quantities, materials, and configurations see Engineering 8.2 Oensities, Therm<1 Conductivities and Heat Capacities of Hest Sinks insulation density, conductivity, capacity 3.7 lbn/ft 0.0208 BTU/hr F ft 1.11 BTU/ft F Concrete density, conductivity, capacity'50 lbn/fthm 0.81 BTU/hrfft 31.5 BTU/ft F note: miniaun conductivity corresponds to maxi<<nxn density, and maxi<<xln conductivity corresponds to minimsn density.Steel density, conductivity, capacity Stainless steel density, conductivity, capacity Contaim>>nt free volune, min/max, cu.ft.Ground Te<<perature (degrees F)Outside Air Temperature, min/max, degrees f HTC for outside surfaces C90 lbn/f tn 28 BTU/hrfft 54.4 BTU/ft F C96 lbn/fthm 15 BTU/hrFft 54.6 BTU/ft F 1,000,000/1,066,000 55-10/100 1.65 BTU/hr ft degrees F below grade te<<perature COLR 20 Cycle 28, Revision 1
~Table 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters em 4 Item/Name Value Remarks: Containnent fan cooler performance Contairment spray flow, min./max, each, gpm Tea@Hin Hax (deg F)(X1068TU/hr) 120 2.05 4.55 2?0 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 1 Delays for CRFCs and Spray Pumps CRFC delay, offsite power available, seconds CRFC delay, offsite power not available, seconds Contaiwent Spray, 1300 gpn each pwp, maxisxsn delay, sec Contaim>>nt Spray, 1800 gpn each pm', mininasn delay, sec Contaiment Design pressure, psig Distance Basement floor to Springline, feet Distance Springline to top of dome, feet 44 28.5.one pap 26.8-two punps 9/(14 w LOOP)60 95 52.5 includes 2.0 sec Sl delay includes 2.0 sec Sl delay This delay is from the time Contaireent Hi-Hi setpoint is reached.lt includes lnstrut>>nt delay and spray line fill time.This delay is from the time of break.8.4 Contairment Sump Hinimum/maxiaus wtX of HaOH Tank 30/35 9.0 Control Systems (Reactor, FU, Przr Level, Turbine, AFM)Tavg versus power Pressurizer pressure and level algorithms SG secondary level algorithm H/A H/A H/A Tavg reaps linearly from 547 degrees F at OX power to 561 degrees F at 100X power Pressurizer pressure setpoint is constant at 2235 psig.Pressurizer level ramps from 35X to 50X for 0 to 100X power (547-561 degrees F).Level remains constant at 52X to 100X power.(Power from turbine 1st stage press,)10.0 10.1 10.1.1 Safety System Setpoints Reactor Protect 1m System Power range high neutrcn flux, high setting nominal accident analysis delay time, sec 1.08 1.18 0.5 10.1.2 Power range high neutron flux, low setting nominal accident analysis 0,240 0.350 COLR 21 Cycle 28, Revision 1
>s RCCAs are released 1.2 sec after setpoint is reached.10.1.12 intermediate range ncminal, RTP safety analysis, RTP delay time, sec 0'5 H/A H/A Hay fluctuate due to core flux Hot explicitly modeled in safety analysis.1.13 Source Range~~~nominal, cps accident analysis, cps delay time, sec 1.DE+5 1.DE+5 2.0 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 Engineered Safety Features Actuation System Safety Tnjecticn System High contai~t pressure Hominal setpoint, psig Accident Analysis setpoint, psig Delay time, sec 4.0 60~34 44 w/LOOP~only modeled in accident analysis for start of contaireent fan coolers.Time delays are for start of contain>>nt fan coolers.10.2.1.2 Lou pressurizer pressure Hominal setpoint, psig 1750 COLR 23 Cycle 28, Revision 1 I Tab'ie 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters Item/Name Value Remarks: Accident Analysis setpoint, psia Delay time, sec 1785, SGTR 1730, non-LOCA 1715, LOCA 2.0 10.2.1.3 Low stem line press~Nominal setpoint, psig Accident Analysis setpoint, psig Delay time, sec 514 372.7 2.0 See Engineering See Engineering 10.2.2 Contai~t Spray Nominal Setpoint, psig Accident analysis setpoint, psig Delay time, sec 28 32~5 28.5 See Engineering Delay time includes time to fill lines.See Engineering 10.2.3 AFM System Low-low stem generator water level 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 11X error has been included to account for the SG level measurement system at a contairvnent teIIyerature of 286 F 10.2.4 Stem Line Isolation 10.2.4.1 High cIntai~t 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 Nemine l Setpoint Accident analysis setpoint Delay time O.CE6 lb/hr equivalent steam flow at 755 psig and Tavg<545 F N/A H/A Note: flow setpoint is below nominal full power flow and therefore this portion of logic is made up at po~er Hot explicitly modeled Hot explicitly modeled.Steam line isolation is assuned 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 H/A Hot explicitly modeled COLR 24 Cycle 28, Revision 1 I'ab e 1:"UPSAR Chapter 15 Analysis Setpoints and Input Parameters em 4 Item/Name Value Remarks: Delay time N/A Not explicitly modeled.Steam line isolation is assuaed concurrent with SI (I.e.2 s delay+5 s valve stroke)10.2.5 10.2.5.1 11.0 Feedwater isolation Nigh stem generator water Level Nominal Setpoint Accident analysis setpoint Delay time BMI Stmm 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 temperature, F Naximzn moisture carryover, X Narro~range level tap Locations, inches above TS secondary face Wide range Level tap locations, inches above TS secondary face 85K of the narrow range instrunent span each SG IOOX of the narrow range instrunent span each SG 2.0 2,602,000,000 Plugging%FLow KLb/hr 0 , 34950 5 34630 10 34280 15~33850 3,264,358 at 877 psia 1085 556 0.10 386//529/8/4/529/e Instrunent 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 po~er, psi Secondary nozzle to nozzle dP Q full power, psi Primary nozzle to nozzle unrecoverable pressure drop vs.plugging, psi 14.7 7.5 Plugging%0 5'0 15 ap psi 31.01 33.27 35:82 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 No.of tubes per SG Tube (I, inches Tube average wall thickness, inches Naximss tube length, ft Hiniaxza 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 28, Revision 1 'abi.e 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters Item/Name Value Remarks: Hinisasa U-bend radius, inches Haxisua 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 Tube material SG Tube Haterial Thermal Conductivity, BTU-in/hr-ft-F 3.979 54,001 47,809 30.427 SB-163 Temp F 200 300 400 500 600 Alloy N06690 Conductivity 93 100 107 114.5 122 54.007 4.044 24.51 303'/u/310'/i/308 182 Hote: this is not the bend radius for the shortest tube.SG Tube Haterial,Specific Heat, BTU/lb-F Distance from top of tube bundle to 33X NRL, ft Teap F 200 300 400 500 600 Conductivity 0.112 0.1155 0.119 0.1225 0.126 5.703 11.3 11.F 1 SG Vol~SG Secondary Side Vol~Secondary voiune, f t (total)Secondary voiune up to lower HRL tap, ft Secondary volune up to upper HRL tap, ft 4512.7 1893.2 3460.4'1.3.2 Riser Vol~Secondary side bundle voiuae (TS to top of U-bend inside shroud), ft'econdary riser voiuoe, top of U-bend to spill-over point, ft 1281.8 507.0 Equivalent to LOFTRAN riser voiune.11.3.3 fancier Vot~Downcomer voiune, top of TS to top of U-bend, ft Downcomer voiuae, top of U-bend to spill.over point, ft'359.6 1437.3SG Primary Side Vol~Inlet plenun per SG, ft Outlet pienun per SG, ft 129.65 129.65 COLR 26 Cycle 28, Revision 1 A 'able 1: UPSAR Chapter 15 Analysis Setpoints and Input Parameters Item/Name Value Remarks: Tube primary volune per SG, f t Primary total volune per SG, ft Circulation ratio (100X pwer, clean, unplugged) Tubesheet thickness, inches 710.3 969.6 5.39 25.625 Circulation ratio~bundle flol5/steam floe.Assunes 40,000 ibm/hr bl ow5ovn.Includes cladding.11 4 11.5 SG Primary Side Dimemlm>>Primary head radius, inches Divider plate thickness, inches inlet and outlet nozzle, inside diameter cylindrical section, inches Nozzle divergence angle, degrees Nozzle inside diameter at plenun, inches Nozzle lengths, inches Heigth fran SG primary heed bottom (outside)to top of TS, inches Distance tube sheet primary face to hot leg centerline, ft SG Secondary Side Dimensions Lover shell inside diameter, inches LoMer shell thickness, inches Tube shroud inside diameter, inches Distance top of tube bundle to top of steam nozzle, inches Steam nozzle floN restricter area, ft'istance secondary face of TS to centerline of feedvater 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 58.375 1.875 31.200 11'30'7.0 ,cylindrical section conical section total length 90/,e 6.654 122 2.875 114 298.5 1,4 407/0 374 41.64 178.0 Nozzles, head 60 Tubes 60 8.75 13.0 21.75 Radius to clad surface.This value is total area inside shroud.This value is equivalent to the riser height for the OSG.Values given are conservative assu5ytions. 11.6 SG Secondary Side Mater Nasses Secondary Mater inventory, 100X poger, T~=573.5, no plugging, ibm Secondary eater inventory, 100X poMer, T 559, no plugging, lba 11.7 SG Primry Side Head Loss Coefficients 86,259 liquid 5,286 steam 85,547 liquid 4,675 steam Best estimate value.Best est imate va lue.COLR 27 Cycle 28, Revision 1 ~Table 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters em 4 Item/Name Value Remarks: SG inlet nozzle/planus Loss coefficient, ft/gpm'G outlet nozzle/plenun loss coefficient, f t/gpn SG tubing loss coefficient, ft/gpn SG tubing loss coefficient, straight section (in), ft/gpn'G tubing loss coefficient, U-bend section, ft/gpm'G tubing Loss coefficient, straight section (out), ft/gpn'.01E-09 for lD*31.2>>3.31E-10 for ID>>31.2>>9.62E-09 for OX plugging 1.32E-08 for 15X plugging 4'9E-09 for OX plugging 5.73E.09 for 15X plugging 1.02E-09 for OX plugging 1.40E-09 for 15X plugging 4.41E.09 for OX plugging 6.08E-09 for 15X plugging For tube ID>>0.664", Ao>>11.C58 ft, Au>>9.739 ft.Plugging is assuned to be uniform.for tube LD=0.664", A=11.C58 ft, Au>>9.739 ft.Plugging is assumed to be uniform.For tube ID=0.664", A=11.458 ft, Au>>=9.739 ft.Plugging is assuned to be uniform.For tube LD=0.664>>, A,>>11.458 ft, Au>>9.739 ft.Plugging is assuned to be uniform.COLR 28 Cycle 28, Revision 1