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
COLR GINNA STATION Cycle 28 Revision t CORE OPERATING LIIVIITS REPORT (COL R)
Re ponsible Hanaget H/IE/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 3 2.1 SHUTDOWN MARGIN . 3 2.2 MODERATOR TEMPERATURE COEFFICIENT . 3 2.3 Shutdown Bank Insertion Limit . 3 2.4 Control Bank Insertion Limits . 4 2.5 Heat Flux Hot Channel Factor (Fo(Z)) ~ ~ ~
2.6 Nuclear Enthalpy Rise Hot Channel Factor (F"~ ) 4 2.7 AXIAL FLUX DIFFERENCE . ~ ~ ~ ~ ~ ~ ~ 4 2.8 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 5 2.9 Boron Concentration . ~ ~ ~ ~ ~ 5 3.0 UFSAR CHAPTER 15 ANALYSIS SETPOINTS AND INPUT PARAMETERS ..... 5
4.0 REFERENCES
6
- REQUIRED SHUTDOWN MARGIN . . . . . . . . . . . 7 FIGURE 1 . . . . . . . . .
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 10 TABLE 1 - UFSAR CHAPTER 15 ANALYSIS SETPOINTS AND INPUT PARAMETERS. 11 COLR Cycle 28 Revision 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 "SHUTDOWN MARGIN (SDM)"
3.1.3 "MODERATOR TEMPERATURE COEFFICIENT (MTC)"
3.1.5 "Shutdown Bank Insertion Limit" 3.1.6 "Control Bank Insertion Limits" 3.2.1 "Heat Flux Hot Channel Factor (Fo(Z))"
3.2.2 "Nuclear Enthalpy Rise Hot Channel Factor (F"~)"
3.2.3 "AXIAL FLUX DIFFERENCE (AFD)"
3.4.1 "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits" 3.9.1 "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 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.
2.1.3 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 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)
F (Z) s ~F /*K(Z) when P > 0.5 P
Fo(Z) ~ QFog*K(Z) when P s 0.5
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 The AXIAL FLUX DIFFERENCE (AFD) target band is + 5%. The actual target bands are provided by Procedure RE-11. 1.
2.7.2 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 The pressurizer pressure shall be > 2205 psig.
2.8.2 The RCS average temperature shall be s 577.5 F.
2.8.3 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 ZIRLO' Cladding 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
ACCEPTABLE 2.5 (0.2 45)
OPERATION (0.2 40)
~ ~
MO O
b (0,1,80)
D Q
LLJ rL 1.5 z (1500.1,45)
I I
1 (1500,1,00) I P-D x(o UNACCEPTABLE 0.5 OPERATION 0
1500 1000 500 COOLANT BORON CONCENTRATION (ppm)
D I DDT << I \ D << ~ MTW T I TDD ~ MTW ANTE:
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
220 1em.') 66.6, 200 B Bank (tel. $ 64) 1 80 160 (0,164 C Bank
'B I(0 140 CL 120 ank
~
O
~ 100 V)
O 80 CL 60 (0, 53) 6$
40
~ CL 20 (30.
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
Q.
I 06 C$
Total Fo
= 2.450
~
C
~
X E~ft 0.0
~K 1.0 0.4 11.783 1.0 QP
~
N
~
lg 202 0
R 0,0 0.0 2.0 4.0 6.0 8.0 10.0 11.783 Elevation (ft)
FIGURE 3 K(Z) NORMALIZED Fq(Z) AS A FUNCTION OF CORE HEIGHT COLR Cycle 28, Revision I
00 NOT OPERATE IN THIS AREA WITH AFD OUTSIOE THE TARGET BAt4)
(.11,90) (11/0) 80 ACCEPTABl.E
~O OP ERAT)ON a
"--'-- " "'UTSDEWlTH AFD BAND THE'AROET WlTH <<1 t%
PENALTY Q 60 DEVIATlON Q. THE (41,60) (31,60) x 40 a
ACCEPTABLE .
I~ OP ERAT)ON 20
-30 -20 -10 0 10 20 30 AXIALFLUX 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 300.0 Above upper support plate.
Upper PL'enure volune, fts 580.2 Bottom of upper core plate to top of upper support plate. Includes outlet holes in the barrel.
Top of fuel volte, ft 50.3 Top of active fuel to bottcm of upper core plate, inside barrel baffle.
Inlet nozzle(s) volma, total of two, ft 43.2 Outlet nozzle(s) volune, total of two, ft 37.4 Includes nozzle forging protrusion into vessel. Does not include mating hole in barrel, this is included in the Upper PLenua volune.
Active fuel volume, ft 367.6 Bottom of fuel to top of fuel Bottom of fuel volune, ft 11.0 Top of lower core plate to bottom of active fuel.
Lover PLefwn volte, ft 514.3 Below top of lower core plate Downcomer volune, above bottom of cold leg, ft 138.4 Above bottcm of cold leg elevation tc bottom of upper support plate Downcomer, lo~er core plate to elevation of the 278.2 Top of lower core plate to elevation bottom of the cold Leg volune, of bottom of cold leg baffle, lower core plate to upper core 128. 5 Top of lower core plate to bottcm of ft'arrel plate volte, upper core plate.
volte, Includes nozzl es ft'otal fthm 2449.1 Hot leg pipe volune per loop volune, fto 78.7 Cold leg volune per loop + cross over, fts cross over = 140.7 cold leg ~ 46.8 RC purp volune per pm@, ft 192 Cold Leg pipe ID, in./Pwp suction ID, in. 27.5/31 Hot Leg pipe IO, in. 29 (28.969)
Design pressure, psig 2485 Design temperature, F 650 Cold Leg and Hot Leg Centerline Elevation 246'0" Reactor Coolant Puap Head-Capacity and NPSH curves for reactor See Engineering Homologous Curves are available in coolant pNps/Homologous Curves RETRAH Rated RC pap head and flow, ft & gpll 252; 90,000 Rated RC pump torque and efficiency Q rated 84K efficiency at hot head/flow, ft-lb, fraction condi t I ons RCP Pmp Rated Power (hot, 556 degrees F) 4842 BHP RCP Hotpr Rated Speed, RPH 1189 Homent of inertia of punp and motor, Lb-ft'C 80,000 pump heat, HQt (max/min per pap) 5, 4 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 1520 Reactor power tncertainty, X RTP Bypass, X 6.5 Thimble plugs removed.
Upper head bypass, X M proprietary Upper head tenyerature, degrees F 590 High T value.
Heat transfer area, ft 26,669 Average core heat flux, Btu/hr-ft 189,440 1.3 Fuel Assemblies 1.3.1 Height Total, inches ( length from bottom of assenhly to 159,935 top nozzle)
Fuel Rod Length, inches ( length from bottom of 149. 138 pin to top of pin)
Active, inches 141.4 1.3.2 Fuel Assembly Geometry Hass of fuel, lbn 105,500 Hass of clad, ibm 25,927 Hunber of fuel pins per fuel assenhty (FA) 179 Ho. of Fuel Assemblies 121 Fuel pin pitch, in. 0.556 Bottom nozzle weight and volune 9.1 lbs.
31.5 in Top nozzle, w/ insert, weight and volune 18.15 lbs.
62.9 inn Fuel Assembly resistance [core dP f(flow)],,psi core delta P ~ 20 psi Thimble plugs removed.
f( lb/hr) Q flow ~ 170,200 gpn Fuel Assenhly free flow area, in 34.75 Single assembly.
1.3.3 Fuel pin geometry Pellet diameter, in. 0.3444 Clad OD/ID, in./in. 0.400/0.3514 1.3.4 Control Rod C Tnstnmat Guide T~
Ho. of control rod guide tubes 16 Ho. of instrunent guide tubes Control Rod Guide tube upper part (X)/ID, in./in. 0.49/0.528 instrunent Guide tube OD/1D, in. /in. 0.395/0.350 Guide tube lower part OD/1D, in./in. 0.4445/0.4825 Control Rod Drop Times, maxinuns, sec. Kon-LOCA 2.4 Allowances are added to the Tech Spec LOCA 3.0 allowable value.
Control rod maxinun withdrawal rate, in./min. 45 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. 90 Control rod insertion limits See COLR Hot charnel radial peaking factor 1.75 Heat Flux Hot channel factor FQ 2.45 1.4 Pressurizer Code safety valve flow capacity, ibm/hr 288,000 Rating at 2485 psig plus 3X accuml at i on Code safety valve open time 0.8 sec seal clearing time Crosby Hodel HB-BP-86, size 4K26 Code safety valve setpoint 2485 psig Tolerance is + 2.4X/-3X.
Spray valve 2 Spray valve flow capacity, gpa/valve 200 Spray valve setpoint- start open/full open 2260/2310 Proportional Spray valve time constant, sec ~ 5 Assumed value PORV nunber 2 PORV f low capacity, ibm/hr 179,000 Steam flow at 2335 psig PORV Cv 50 gpm/(paid)1/2 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.
PORV open time 1.65 sec + transmitter LTOPs transmitter is Foxboro E11GH.HSAE1, with a time response of 1 sec (time to 90X of final value for step input)
PORV close time 3.95 sec + transmitter LTOPs transmitter is Foxboro E11GH-HSAE1, with a time response of 1 sec (time to 90X of final value for step input)
PORV setpoint [normal) open/close, psig 2335/2315 PORV setpoint (LTOP) open/close, psig 430 PORV blowdown characteristic Hester capacity w/ bank capacity and setpoints, 800 kM Control banks 0 kM at 2250 psig and 400 kM at 2220 psig Backup Heaters Full on at 2210 psig and resets at 2220 psig Hiniaasn heater capacity required for LOOP, kM 100 Heater bank controller type proportional 400 kM 1.4.1 Pressurizer vol~(s) (100X / OX power)
Mater, ft'100X / OX power) 396/199 Steam, ft (100X / OX power) 404/601 Total, fts 800 Pressurizer iD, ft-in 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. '8.75 Surge line is 10 in schedule 140 Spray line 10, in. 3.062 Surge line volume, fthm 18.4 1.4.2 Pressw izer Level Lower level tap elevation 257' Upper Level tap elevation 275' Pressurizer level vs X power Xpower Level Pressurizer level is ramped linearly 0 X 35X between these points. Hot used in 100 X 50X Chapter 15 analyses.
Distance Hot Leg Centerline to Lower Tap, ft 10.750 Haxiaxm level allowed for steam bubble, X 87 1.5 RCS FLows, Tcaperature and Pressures Total reactor coolant flow, gpm (15X plugging) 170,200 Use for non DNB Total reactor coolant flow, gpn (15X plugging) 177,300 Use for statistical DHB to 573.5/547 Cycle 28 T -" 561 Average reactor coolant teeperature, degrees F 559 ,
(Full power/HZP)
Reactor coolant pressure, psig 2235 Reactor coolant flow mcertainty, X nominal Reactor coolant tetperature certainty, degrees F
Reactor coolant pressure mcertainty, psi s 30 DNB Limit (safety analysis limit) 1.40 1.6 Low Temperature Overpressure Protection (LTOP)
Hiniaam RCS vent size, square inches
~No. of SI ixsrps capable of injection 0/1 (PORVs/vent)
Haxinam pressurizer level for RCP start, X 38 1.7 Fuel Handling/Dose Calculaticns Haxitmm reactor coolant gross specific activity 100/t pCi/gm Haxinxm reactor coolant dose equivalent i-131 1 ~ 0 pCi/gm Haxitmm secondary coolant dose equivalent I-131 0.1 pCi/gm kininam reactor coolant boron concentration, ppm 2000 Hinilmm reactor coolant Level 23 ft above flange Hinicxm spent fuel pool Level 23 ft above fuel Hlnlaxm spent fuel pool boron concentration, ppm 300 Hinislm spent fuel pool charcoal filter 70 TS testing requires 90X eff.
efficiency, X methyl iodine removaL Hiniaxm post accident charcoal filter 70 TS testing requires 90X eff.
efficiency, X methyl iodine removal 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, 70 TS testing requires 90X eff.
X methyl iodine removal HInisass time between reactor criticality and 100 fuel movement, hrs.
Source Terse used for dose calculations ORGEN 2 Dose conversion factors ICRP-30 Haxisxza Gas Decay Tank Xenon.133 concentration, 100,000 Ci 2.0 Hain Feedwater (HFM)
Feedwater tesperature versus load Power Teeperature 100X design teffp is 432 degrees F 102X 425 F 70X 385 F 30X 322 F OX 100 F Feedwater Suction Temperature vs Power, nominal Power Temperature 98X 345 F 70X 319 F 50X 295 F 30X 259 F Feedwater Suction Pressure vs Po~er, nominal Power Pressure 98X 277 psig 70X 282 psig SOX 305 psig 30X 370 psig Head-Capacity and NPSN curves Head-Capacity and NPSN curves for main feedwater See Engineering Selected flow splits are provided for Fxmps model validation.
Hain Feedwater Ixgp - Rated Head Hain Feedwater pmp - Rated Torque 2150'89.612 Hain Feedwater punp ~ Homent of Inertia Elevation of steam generator inlet nozzle Elevation of main feedwater pump, ft 257. 75 Elevation is at center of shaft Elevation of condensate punp, ft 250.833 HFM regulating valve open time on demand, sec HFM regulating valve close time on demand, sec 10 HFll regulating valve Cv, full stroke 725 Assuned value. Actual value = 684.
Low load HFll regulating valve Cv, (bypass l8.7 Effective Cv: includes bypass line valves)
HFM Neater resistance (delta P) see Engineering Design data on the Nigh Pressure Heaters (2 in parallel) is provided 3.0 Auxiliary Feedwater (AFM)
Hinieasn design temperature of the water source 30, 32 Initial AFM ~ster source are the CSTs service ~ster / CST (degrees F) located in the Service Bldg. Safety Related source is the Service Mater system ( I eke) .
Haxisxsa design tecperature of the water source 80, 100 Initial AFM water source are the CSTs service water / CST (degrees F) 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, ~TDAFM starts on LO level (17K) in SCC 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 HiniImNI delay for AFM start, sec TDAFM . 0, HDAFM 1 NOAFM acceleration time test results show approximately 1.5 s.
HaxiImsn delay for AFM start, sec Increased time of 600 sec. will be used in future analysis AFM control valve open time on demand, sec H/A HDAFM control valves are normally open and throttle closed to control flow between 200 '30 gpm AFM control valve Cv[flow is f(dP)) HDAFMP valves are 3 Rockwell model ¹ A4006JKHY stop check valves. TDAFM control valves (4297, 4298) are 3 Fisher ¹470-HS.
TDAFMP, maxiImsn flow, gpm 600 AFM, minirmIII flows, both generators intact, gpm TOAFMP 200/SG SBLOCA assunes 200 gpn per SG with HDAFMP 200/SG the fai lure of one OG HiniImmI delay for standby AFM start, min 10 4.0 Nein Stem System (NS)
Location (and elevation) of condenser ckmp CSO . elev 256'.875 valves and atmosphcl"Ic I'clicf valves ARV - elev 289'.563 Full load steam line pressure drop, psi approx 45 This estimate, to the governor valves, is provided for comparison purposes only.
HS Isolation valve close time [full open to full HSIV - 5.0 The check valve is asswIed to close close) close. time, sec check valve - 1.0 in 1 sec under reverse flow.
NS Isolation valve Cv [flow is f(dP)) HSIV - 23500 check valve . 17580 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 1110 0 bank (4 valves), ibm/sec. 1115 40 1120 91 1125 141 1131 191 1136 222 1141 223 1151 225 1161 227 1166 228 1173 342 1181 494 1190 ~ 646 1200 799 1205 859 1209 920 1211 931 Nunber of valves in bank Valve setpoint(s), (first/last three), nominal, 1085/1140 Valves are. Crosby ¹HA-65 6R10 psig Setpoint tolerance is +1X -3X. /
Nodel valve setpoint at 1.01 (nominal), and full flo11 at 1.04 (nominal).
Valve bloudo1a1 characteristic 15X max 1 SMS Atmospheric relief valves No. Atmospheric relief valves Atmospheric relief valve setpoint/Air-operated, 1050 During Hot Standby operation setpoint ps 1 9 is Lowered to control no load Tavg Atmospheric reLief valve setpoint/Booster, psig 1060 Atmospheric relief valve capacity, Lbn/hr 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 ASS1N1ing close time = opening time Condenser cANp valve setpoint(s) for TT: Tavg>555 4 valves, On TT valves control open at 6.7X/F
>563 4 valves; (PID) above 547 111th full open no TT: Tref +12 4 valves, setpoints as described. On 10X step Tref+20 4 valves load decrease same ratio with a 6F deadband from Tref Condenser dip valve Cv [floe is f(dP)) 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
- 8 pcsto are PDPs seals - 3 w/ 46 gpm total gp11 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 15 Type of controller (e.g., P + I) and gains 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 Emergency Core Cooling System (ECCS) 7.1 ECCS Delivery vs RCS Pressure 7.1.1 Residual Heat Removal (RHR) Delivery vs RCS Pressure Ninisass RHR Delivery, train failure RCS Pressure Delivery LOCA Appendix K case. Train failure (psia) (gpm) results in one pup running with 10X 155 0 degradation with one line blocked.
152 0 150 0 140 250 120 648 100 &36 80 985 60 1115 40 1232 20 1338 14.7 1365 Nininasa RHR Delivery, two Ixmps ruwing, one RCS Pressure Delivery LOCA Appendix K case (offsite po~er line blocked (psia) (gpm) available). Two pcs running with 155 0 10X degradation with one line 154 0 blocked.
152 160 150 252 140 516 120 830 100 1056 80 1243 60 1406 40 1552 20 1686 14.7 1720 7.1.2 Safety Injection (Sl) Delivery vs RCS Pressure Nininua SI delivery, 2 Ixmps operating, one line Press Delivery Spill LOCA Appendix K case. Train failure spilling (psig) (gpn) (gpm) results in two Ixmps running with SX 1375 0.0 465 degradation with one line spilling to 1300 62 465 contaireent.
1200 125 465 1100 167 465 1000 201 465 900 229 465 800 253 465 700 273 465
.600 289 465 500 305 465 400 321 465 300 336 465 200 352 465 100 368 465 0 384 465 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 Press Delivery (gpm) Used for non-LOCA transients, SX pump (psia) Loop 'A' Loop degradation BI 1390 16 19 1315 87 97 1215 147 163 1115 193 214 1015 231 257 915 266 295 815 297 329 715 325 360 615 352 390 515 377 418 415 400 444 315 423 469 215 445 493 115 465 516 15 485 538 Hinisxsa Si delivery, 2 pwys operating non-LOCA Press Delivery (gpm) Used for non.LOCA transients, 5X punp (psia) Loop 'A'BI Loop degradation.
1390 8 8 1315 69 71 1215 121 126 1115 162 169 1015 197 206 915 228 239 81$ 255 269 715 281 296 615 305 322 515 328 346 415 350 369 315 37D 391 215 390 412 115 409 432 15 427 452 Hex(asm Si delivery, 3 pcs operating, SGTR Press Loop A Loop B The KYPIPE model asswes no (psig) (gpn) (gpm) Loop A and B pressures pm'egradation.
1375 76 84 are set equal. Used for SGTR.
1300 128 141 1200 180 198 1100 221 245 1000 258 285 900 290 321 800 320 354 700 348 385 600 374 413 500 398 440 400 421 466 300 443 490 200 464 514 100 485 536 0 504 558 7.3 Acnmslators Nwker of accumulators 2 Total volune, each, fts 1750 Liquid volune, fts - min/max 1111/1139 Liquid volune, ft' Best Estimate 1140 initial pressure, psig - Hinisxla / Haxinua 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 105 LBLOCA Boron concentration, ppm (min/max) 2100/2600 Hote . EQ analyses use a maxi<<un concentration of 3000 ppn 7A RMST RMST Te<<perature, min / max, degrees F 60 / 80 Upper limit increased to 104 Ninitmsn RMST volw>>, gal 300,000 RMST boron concentration, ppm (min/max) 2300/2600 Note - EQ analyses use a maxinxin concentration of 3000 ppn 8.0 Conte i ~t initial contairment pressure, psia min - 14.5 lfinitmjn is used for LOCA analysis.
max - 15.7 Haxi<<xsn is used for the containment integrity cases (SLB).
initial contaim>>nt te<<perature (LOCA/SLB) 90/120 LOCA te<<perature lower for PCT degrees F calculations. SLB higher for
~
contaim>>nt integrity initial relative hunidity,
'0 X
SM temperature min/max, degrees F 30/$ 5 Haxitmln contaim>>nt leakage, wtX/day 0.2
" Contairment Heat Sinks Listing of Passive Heat Sinks, quantities, materials, and configurations see Engineering lbn/fthm 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 note: miniaun conductivity 0.81 BTU/hrfft corresponds to maxi<<nxn density, and 31.5 BTU/ft F maxi<<xln conductivity corresponds to minimsn density.
Steel density, conductivity, capacity C90 lbn/f tn 28 BTU/hrfft 54.4 BTU/ft F Stainless steel density, conductivity, capacity C96 lbn/fthm 15 BTU/hrFft 54.6 BTU/ft F Contaim>>nt free volune, min / max, cu. ft. 1,000,000 / 1,066,000 Ground Te<<perature (degrees F) 55 below grade te<<perature Outside Air Temperature, min / max, degrees f -10 / 100 HTC for outside surfaces 1.65 BTU/hr ft degrees F 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 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 Contairment spray flow, min./ max, each, gpm 1300 / 1800 1
8.3 Delays for CRFCs and Spray Pumps CRFC delay, offsite power available, seconds includes 2.0 sec Sl delay CRFC delay, offsite power not available, seconds 44 includes 2.0 sec Sl delay Contaiwent Spray, 1300 gpn each pwp, maxisxsn 28.5 . one pap This delay is from the time delay, sec 26.8 - two punps Contaireent Hi-Hi setpoint is reached. lt includes lnstrut>>nt delay and spray line fill time.
Contaim>>nt Spray, 1800 gpn each pm', mininasn 9 / (14 w LOOP) This delay is from the time of break.
delay, sec Contaiment Design pressure, psig 60 Distance Basement floor to Springline, feet 95 Distance Springline to top of dome, feet 52.5 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 H/A Tavg reaps linearly from 547 degrees F at OX power to 561 degrees F at 100X power Pressurizer pressure and level algorithms H/A Pressurizer pressure setpoint is constant at 2235 psig . Pressurizer level ramps from 35X to 50X for 0 to 100X power (547 - 561 degrees F).
SG secondary level algorithm H/A Level remains constant at 52X to 100X power. (Power from turbine 1st stage press,)
10.0 Safety System Setpoints 10.1 Reactor Protect 1m System 10.1.1 Power range high neutrcn flux, high setting nominal 1.08 accident analysis 1.18 delay time, sec 0.5 10.1.2 Power range high neutron flux, low setting nominal 0,240 accident analysis 0.350 COLR 21 Cycle 28, Revision 1
Table 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters Item/Name Value Remarks:
delay tilllc, scc 0.5 10.1.3 Overtcmpera~ delta T nominal Variable accident analysis Variable delay time, scc 6.0 Total delay time - from the time the temperature difference In the coolant loops exceeds the trip setpoint until the rods are free.to fall 10.1.4 Overpcwer delta T nominal Variable accident analysis Variable Hot explicitly modelled in safety analysis delay time, sec 2.0 10.1.5 High pressurizer prcssure nominal, psig accident analysis, psia 2410 delay tilllc~ scc 2.0 10.1.6 Lou pressurizer pressure nominal, psig 1873 accident analysis, psia 1775 (non-LOCA) 1730 (LOCA) 1905 (SGTR) delay timey scc 2.0 10.1.7 Lou reactor coollHlt flow nomina l 91X of normal indicated fiou accident analysis 87X per loop delay time, sec 1.0 10.,1.8 Lcw-lou SG level nominal 17X of the narrow range Hhlle trip setpoint could be as loll level span as 16X, AFM initiation limits to 17X accident analysis OX of narrow range level span delay time, sec 2.0 10.1.9 Turbine Trip (lou fluid oil pressure) nolllina l i ps l 9 45 accident analysis M/A Hot explicitly modeled in safety analysis delay time, sec 2.0 COLR 22 Cycle 28, Revision 1
'able 1: UPSAR Chapter 15 Analysis Setpoints and Input Parameters em 4 Item/Name Value Remarks:
10.1.10 Unck~l tage nominal, V 3150 accident'nalys is Safety analysis assunes RCCAs are released 1 ' sec. after setpoint is released.
delay time+ sec 1.5 10.1.11 Underfrequency nominal, Hz 57.7 accident analysis 57.0 Analysis is performed but not explicitly modeled in safety analysis.
delay 't'Ime 1.2 Safety analysis assw>>s RCCAs are released 1.2 sec after setpoint is reached.
10.1.12 intermediate range ncminal, RTP 0 '5 Hay fluctuate due to core flux safety analysis, RTP H/A Hot explicitly modeled in safety analysis delay time, sec H/A
.1.13
~ ~ Source Range nominal, cps
~
- 1. DE+5 accident analysis, cps 1.DE+5 delay time, sec 2.0 10.1.14 High Pressurizer level nominal 0.90 accident analysis 0.938 delay time, sec 2.0 10.2 Engineered Safety Features Actuation System 10.2.1 Safety Tnjecticn System 10.2.1.1 High contai~t pressure Hominal setpoint, psig 4.0 Accident Analysis setpoint, psig 60~ ~only modeled in accident analysis for start of contaireent fan coolers.
Delay time, sec 34 Time delays are for start of 44 w/ LOOP 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 1785, SGTR 1730, non-LOCA 1715, LOCA Delay time, sec 2.0 10.2.1.3 Low stem line press~
Nominal setpoint, psig 514 Accident Analysis setpoint, psig 372.7 See Engineering Delay time, sec 2.0 See Engineering 10.2.2 Contai ~t Spray Nominal Setpoint, psig 28 Accident analysis setpoint, psig 32 ~ 5 See Engineering Delay time, sec 28.5 Delay time includes time to fill lines. See Engineering 10.2.3 AFM System Low-low stem generator water level Nominal Setpoint 17 X of narrow range instrunent span each steam generator Accident analysis setpoint 0 X of narrow range A positive 11X error has been instrunent span each steam included to account for the SG level generator measurement system at a contairvnent teIIyerature of 286 F Delay time, sec 2.0 10.2.4 Stem Line Isolation 10.2.4.1 High cIntai~t pressure Nominal Setpoint, psig 18 Accident analysis setpoint H/A Not explicitly modeled Delay time H/A Not explicitly modeled 10.2.4.2 High stem flow, coincident with low Tavg and SI Nemine l Setpoint O.CE6 lb/hr equivalent steam Note: flow setpoint is below nominal flow at 755 psig and Tavg < full power flow and therefore this 545 F portion of logic is made up at po~er Accident analysis setpoint N/A Hot explicitly modeled Delay time H/A 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 3.6E6 lb/hr equivalent steam flow at 755 psig Accident analysis setpoint 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 Feedwater isolation 10.2.5.1 Nigh stem generator water Level Nominal Setpoint 85K of the narrow range instrunent span each SG Accident analysis setpoint IOOX of the narrow range instrunent span each SG Delay time 2.0 Instrunent Loop only 11.0 BMI Stmm Generators Heat Load per SG, BTU/hr 2,602,000,000 Primary flow per SG, KLb/hr Plugging% FLow KLb/hr Design flows at T,~ = 573.5 F 0 , 34950 5 34630 10 34280 15 ~ 33850 Steam flow per SG, lb/hr (clean, unplugged) 3,264,358 at 877 psia Conditions for T,~ = 573.5 F Secondary design pressure, psig 1085 Secondary design temperature, F 556 Naximzn moisture carryover, X 0.10 Narro~ range level tap Locations, inches above 386/ / 529/
TS secondary face Wide range Level tap locations, inches above TS 8/4 / 529/e secondary face SG Pressure Drops Secondary nozzle to nozzle dP Q full po~er, psi 14.7 Value is total static pressure drop.
Secondary nozzle to nozzle dP Q full power, psi 7.5 Pressure drop from top of U-bend to outlet.
Primary nozzle to nozzle unrecoverable pressure Plugging% ap psi See associated flows for X plugging.
drop vs. plugging, psi 0 31.01
'0 5 33. 27 35:82 15 38.72 11.2 No. of tubes per SG 4765 Tube (I, inches 0.750 Tube average wall thickness, inches 0.043 Naximss tube length, ft 70.200 Includes Length in tubesheet (2x25.625")
Hiniaxza tube length, ft 55.925 Includes Length in tubesheet (2x25.625")
Average Length, ft 61.988 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 3.979 Hote: this is not the bend radius for the shortest tube.
Haxisua U.bend radius, inches 54.007 U-bend radius of shortest tube(s), inches 4.044 Average U-bend radius, inches 24.51 Tube straight length (one side) above secondary 303'/u / 310'/i / 308 182 face, inches (min/max/average)
Secondary heat transfer area, ft per SG 54,001 Primary heat transfer area, ft per SG 47,809 Overall bundle height, ft above secondary face 30.427 of TS Tube material SB-163 Alloy N06690 SG Tube Haterial Thermal Conductivity, Temp F Conductivity BTU-in/hr-ft -F 200 93 300 100 400 107 500 114.5 600 122 SG Tube Haterial,Specific Heat, BTU/lb-F Teap F Conductivity 200 0.112 300 0.1155 400 0.119 500 0. 1225 600 0.126 Distance from top of tube bundle to 33X NRL, ft 5.703 11.3 SG Vol~
11.F 1 SG Secondary Side Vol~
Secondary voiune, ft (total) 4512.7 Secondary voiune up to lower HRL tap, ft 1893.2 Secondary volune up to upper HRL tap, ft 3460.4'1.3.2 Riser Vol~
Secondary side bundle voiuae (TS to top of U- 1281.8 bend inside shroud),
riser voiuoe, top of ft'econdary U-bend to spill- 507.0 Equivalent to LOFTRAN riser voiune.
over point, ft 11.3.3 Downcomer ft ft'359.6 fancier Vot~
Downcomer point, voiune, top of voiuae, top of U-bend to TS to top of U-bend, spill. over 1437.3 SG Primary Side Vol~
Inlet plenun per SG, ft 129.65 Outlet pienun per SG, ft 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, ft 710.3 Primary total volune per SG, ft 969.6 Circulation ratio (100X pwer, clean, unplugged) 5.39 Circulation ratio ~ bundle flol5 /
steam floe. Assunes 40,000 ibm/hr bl ow5ovn.
Tubesheet thickness, inches 25.625 Includes cladding.
11 4 SG Primary Side Dimemlm>>
Primary head radius, inches 58.375 Radius to clad surface.
Divider plate thickness, inches 1.875 inlet and outlet nozzle, inside diameter 31.200 cylindrical section, inches Nozzle divergence angle, degrees 11'30'7.0 Nozzle inside diameter at plenun, inches Nozzle lengths, inches ,cylindrical section 8.75 conical section 13.0 total length 21.75 Heigth fran SG primary heed bottom (outside) to 90 /,e top of TS, inches Distance tube sheet primary face to hot leg 6.654 centerline, ft 11.5 SG Secondary Side Dimensions Lover shell inside diameter, inches 122 LoMer shell thickness, inches 2.875 Tube shroud inside diameter, inches 114 Distance top of tube bundle to top of steam 298.5 nozzle, inches Steam nozzle floN restricter area, 1,4 secondary face of TS to centerline of ft'istance 407 /0 feedvater nozzle, inches Distance secondary face of TS to centerline of 374 feed ring, inches Cross-sectional area of tube bundle, ft 41.64 This value is total area inside shroud.
Distance top of tube bundle to spill-over point, 178.0 This value is equivalent to the riser inches height for the OSG.
Primary side roughness, micro-inches Nozzles, head 60 Values given are conservative Tubes 60 assu5ytions.
11.6 SG Secondary Side Mater Nasses Secondary Mater inventory, 100X poger, T~ = 86,259 liquid Best estimate value.
573.5, no plugging, ibm 5,286 steam Secondary eater inventory, 100X poMer, T 85,547 liquid Best est imate va lue.
559, no plugging, lba 4,675 steam 11.7 SG Primry Side Head Loss Coefficients 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 for lD
- 31.2>>
outlet nozzle/plenun loss coefficient, 3.31E-10 for ID>> 31.2>>
ft/gpn tubing loss coefficient, ft/gpn 9.62E-09 for OX plugging For tube ID>> 0.664", Ao>> 11.C58 SG 1.32E-08 for 15X plugging ft, Au>> be9.739uniform.
ft . Plugging is SG (in), ft/gpn'G ft/gpn'.01E-09 tubing loss coefficient, straight section 4 '9E-09 for OX plugging 5.73E.09 for 15X plugging assuned ft, to for tube LD = 0.664", A = 11.C58 Au>> 9.739 ft . Plugging is assumed to be uniform.
tubing loss coefficient, U-bend section, 1.02E-09 for OX plugging For tube ID = 0.664", A = 11.458 ft/gpm'G 1.40E-09 for 15X plugging ft, Au>> = 9.739 ft . Plugging is assuned to be uniform.
tubing Loss coefficient, straight section 4.41E.09 for OX plugging For tube LD = 0.664>>, A,>> 11.458 (out), 6.08E-09 for 15X plugging ft, Au>> 9.739 ft . Plugging is assuned to be uniform.
COLR 28 Cycle 28, Revision 1