ML17264B108

Rev 0 to Ginna Station Colr,Cycle 27.

ML17264B108
Person / Time
Site:	Ginna
Issue date:	11/14/1997
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
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ML17264B107	List: ML17264B106 ML17264B108
References
NUDOCS 9711240147
Download: ML17264B108 (32)

Text

COLR GINNA STATION Cycle 27 Revision 0 CORE OPERATING LIIVIITS REPORT (COL R)

Responsible manage i(/iw/ev Effective Date Controlled Copy Ho.

9'7ii240i47 97iii7 PDR 'DR ADOCK 05000244'

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 2.0 CORE OPERATING OPERATING LIMITS 2.

2.2 1 SHUTDOWN LIMITS REPORT MARGIN.....

MODERATOR TEMPERATURE COEFFICIENT .

~

~ ~

~ 3 3

3 2.3 Shutdown Bank Insertion Limit . 3 2.4 Control Bank Insertion Limits . 4 2.5 Heat Flux Hot Channel Factor (FQ(Z)) ~ ~

2.6 Nuclear Enthalpy Rise Hot Channel Factor (F"~)

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

4.0 REFERENCES

6 FIGURE - RE(UIRED SHUTDOWN MARGIN .

1 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 "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 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 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.

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.

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 defined as 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) when P s 0.5

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" (LCO 3.2.2)

(Limits generated using Reference 1) 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 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 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 The pressurizer pressure shall be z 2205 psig.

2.8.2 The RCS average temperature shall be z 577.5 F.

2.8.3 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

WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Hethodology, July 1985.

2. 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]

3. WCAP-8385, "Power Distribution Control and Load Following Procedures-Topical Report," September 1974.

4. WCAP-11397-P-A, "Revised Thermal Design Procedure", April 1989.

5. 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 ONE LOOP (0. 2.45)

OPERA'nON 0 ACCEPTABLE OPERATION l1l 2 0' (0, 1.80)

~O LOOP (1500.1.45) OP ERAllON m1 (1 500, 1.00)

UNACCEPTABLE OPERATION xV) 1500 1000 500 COOLANT gpRON CONCENTRATION (ppm)

FIGURE I REQUIRED SHUTDOWN MARGIN COLR Cyc1e 27, Revision 0

220 1834 ~

3 200 B Bank 666,'100,

~380

~ (0, 164 184)

$ <6O CB ank

o. $ 40

~ 120 DBank

.a 100 N

80 CL

~

~ 60 (0,53) ca 40 o 20 (30, 0

0 10 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 Tota( Fz = 2.460 0

~

K

~

6$

K

~E't 0.0

~K 1.0 04 CP 11.783 1.0

~

N

~

l5 F02 0

0.0 0,0 2.0 4.0 6.0 8.0 10.0 11.783 Elevation (ff)

FIGURE 3 K(Z) - NORMALIZED Fo(Z) AS A FUNCTION OF CORE HEIGHT COLR Cyc1e 27, Revision 0

DO NOT OPERATE IN THIS AREA WITH AFD oUTSIOE THE TARCET S~

(-11,90) (11/0) 80 ACCEPTABLE

~O CI OPERATION

"" " "" " "" YAHAFD OUTSaE THE TARO ET BAND WITH <<1 fa PENALTY DEMATION TNE (Q1,60) P1,60)

I- 40 Cl ACCEPTABLE l~ ~ ~ ~

OPERATION

~ ~ y 0~

20 0

-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 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, 300.0 Above upper support plate.

fto ft'pper Plenum volune, 580.2 Bottom of upper core plate to top of upper support plate. Includes outlet holes in the barrel.

Top of fuel volune, fto 50.3 Top of active fuel to bottom of upper plate, inside barreL baffle. 'o Inlet nozzle(s) volune, 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 PLenun volune.

Active fuel volrire, ft3 367.6 Bottom of fuel to top of fuel Bottom of fuel volurre, fto 11.0 Top of Lower core plate to bottom of active fuel.

Lower PLenrgr volune, ftc 514.3 Below top of lower core plate Downcomer volunc, above bottom of cold leg, ft 138.4 Above bottom of cold leg elevation to bottom of upper support plate Downcomer, lower core plate to elevation of the 278.2 Top of Lower core plate to elevation bottom of the cold Leg volune, fts of bottom of cold Leg Barrel baffle, lower core plate to upper core 128.5 Top of Lower core plate to bottom of plate volrmre, ft upper ccrc plate.

Total volunc, fto 2449.1 Includes nozzles Hot leg pipe volte per Loop vair ft> 78.7 Cold leg voluae per Loop + cross over, fti cross over = 140.7 cold Leg = 46.8 RC pmp volunc per pump, f 192 t'old leg pipe ID, In./Purrp suction ID, in. 27.5/31 Hot leg pipe ID, in. 29 (28.969)

Design pressure, psig 2485 Design temperature, F 650 Cold Leg and Hot i.eg Centerline Elevation 246'0u Reactor Coolant Prsrrp Head-Capacity and NPSH curves for reactor See HS&L Homologous Curves are available in coolanz pumps/Homologous Curves RETRAH Rated RC pump head and flow, ft & gpm 252; 90,000 Rated RC pump torque and efficiency 9 rated 84K efficiency at hot head/flow, ft-lb, fraction conditions RCP Prmp Rated Power (hot, 556 degrees F) 4842 BHP RCP Hotor Rated Speed, RPM 1189 Moment of inertia of pump and motor, lb-ftz 80,000 RC pump heat, MMt (max/min per pump) 5, 4 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 1520 Reactor power uncertainty, g RTP Bypass, X 6.5 Thimble plugs removed.

Upper head bypass, g M proprietary Upper head tcngerature, degrees F 590 High T~ value.

Heat transfer area, fthm 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 asscnhty 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, ibm 105,500 Hoss of clad, ibm 25,927 Humber of fuel pins per fuel assembly (FA) 179 Ho. of Fuel Assemblies 121 Fuel pin pitch, in. 0.556 Bottom nozzle weight and votunc 9.1 lbs.

31.5 in Top nozzle, w/ insert, weight and volune 18.15 lbs.

62.9 delta P -"20 psi in'ore Fuel Asserrhty resistance (core dP f(flow)], psi Thimble plugs removed.

f(lb/hr) 9 flow ~ 170,200 gpn Fuel Assembly free flow area, in 34.75 Single assembly.

1.3.3 Fuel pin geometry Pellet diameter, in. 0.3444 Clad 00/IO, in. /in. 0.400/0.3514 1.3 4 Control Rod 4 Instruaent Gurdc Tubes Ho. of control rod guide tubes 16 Ho. of instrunent guide tubes Control Rod Guide tube upper part 00/ID, in. /in. 0.49/0.528 Instrunent Guide tube 00/ID, in. /in. .0.395/0.350 Guide tube lower part 00/ID, in. /in. 0.4445/0.4825 Control Rod Drop Times, maximuns, scc. Hon-LOCA 2.4 Altowanccs are added to the Tech Spec LOCA 3.0 allowable value Control rod maximun withdrawal rate, in./min. 45 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. 90 Control rod insertion limits See COLR Hot channel radial peaking factor 1.75 Heat Flux Hot channel factor Fq 2.45 1.4 pressurizer code safety valve flow capacity, Lbm/hr 288,000 Rating at 2485 psig plus 3X accumulation Code safety valve open time 0.8 sec seal clearing time Crosby Model HB-BP-86, size 4K26 Code safety valve setpoint 2485 psig Tolerance is + 2.4X/-3X.

Spray valve n(rmber 2 Spray valve flow capacity, gpm/vaLve 200 Spray valve setpoint- start open/fulL open 2260/2310 proportional Spray valve time constant, sec. 5 Assed value PORV number 2 pORV flow capacity, Lbm/hr 179,000 Steam flow st 2335 psig pORV Cv 50 gpm/(psid)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 E11GM-HSAE1, with a time response of 1 sec (time to 90K of final value for step input)

PORV close time 3.95 sec + transmitter LTOPs transmitter is Foxboro E11GM-HSAE1, with a time response of 1 sec (time to 90K of final value for step input) pORV setpoint [normal) open/close, psig 2335/2315 pORV setpoint (LTOP] open/close, psig 430 pORV blowdown characteristic Heater capacity w/ bank capacity and setpoints, 800 kif Control banks 0 kW at 2250 psig and 400 kw st 2220 psig gackup Heaters Full on at 2210 psig snd resets at 2220 psig Minimus heater capacity required for LOOP, k'M 100 Heater bank controller type proportional 400 kM 1.4.1 pressurizer volusc(s) (100M / Ly( power)

Lister, ft (100K / OX power) 396/199 Steam, ft (100M / OX power) 404/601 Total, ft 800 pressurizer LD, ft-in 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. 8.75 Surge line is 10 in schedule 140 Spray linc ID, in. 3.062 Surge line volune ft 18.4 1 4.2 Pressurizer Level Lower level tap elevation 257' Upper level tap elevation 275' pressurizer level vs X power %power Level pressurizer level is ramped linearly 0 X 35X between these points. Not used in 100 X 50X Chapter 15 analyses.

Distance Not Leg Centerline to Lower Tap, ft 10.750 Haximm level allowed for steam bubble, X 87 1.5 RCS Plows, Temperature and Pressures Total reactor coolant flow, gpm (15X plugging) 170,200 Usc for non DNB Total reactor coolant flow, gpm (15K plugging) 177,300 Usc for statistical DNB Average reactor coolant tecperature, degrees F 559 to 573.5/547 Cycle 26 T~ = 561 (full power/N2P)

Reactor coolant pressure, psig 2235 Reactor coolant flow uncertainty, X nominal Reactor coolant temperature uncertainty, degrees F

Reactor coolant pressure uncertainty, psi a 30 DNB Limit (safety analysis limit) 1.40 1.6 Low Tcaperature Overprcssurc Protection (LTDP)

Hinimua RCS vent size, square inches No. of Si pcs capable of injection 0/1 (PDRVs/vent)

Haxiaam pressurizer level for RCP start, X 38 1.7 Fuel Handling/Dose Calculations Haxigull reactor coolant gross specific activity 100/b pCi/gm Haximm reactor coolant dose equivalent 1.131 1.0 pCi/gm Haxinxm secondary coolant dose equivalent I-131 0.1 pCi/gm Hinimm reactor coolant boron concentration, ppm 2000 Hinimia reactor coolant level 23 ft above flange Hiniaxm spent fuel pool level 23 ft above fuel Hinimua spent fuel pool boron concentration, ppa 300 Hjnieun spent fuel pool charcoal filter 70 TS testing requires 90K cff.

efficiency, X methyl iodine removal Hinfnxsa post accident charcoal filter 70 TS testing requires 90K eff.

efficiency, X methyl iodine removal COLR 14 Cycle 27, Rev>sion 0

Item g Item/Name Value Remarks:

Minimus control room charcoal filter efficiency, 70 TS testing requires 90X eff.

X methyl iodine removal Minimus time between reactor criticality and 100 fuel movement, hrs.

Source Terms used for dose calculations ORGEH 2 Dose conversion factors ICRP-30 Maximun Gas Decay Tank Xenon-133 concentration, 100,000 Ci 2.0 Main Feedwater (MFII)

Feedwater temperature versus load Power Tecyerature 100X design temp is 432 degrees F 102X 425 F 70X 385 F 30X 322 F DX 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 power, nominal Power Pressure 98X 277 psig 70X 282 psig 50X 305 psig 30X 370 psig 2.1 Head-Capacity and HPSH curves Head-Capacity and HPSH curves for main feedwater Sec HS&L Selected flow splits are provided for pcs model validation.

Main Feedwater pump " Rated Head Main Feedwater purp - Rated Torque Main Feedwater pump - Moment of inertia 2150'89.612 Elevation of stcam generator inlet nozzle Elevation of main feedwater pump, ft 257.75 Elevation is at center of shaft Elevation of condensate pump, ft 250.833 MFII regulating valve open time on demand, sec MFII regulating vaLve close time on demand, sec 10 MFII regulating valve Cv, full stroke Assuned value. Actual value -"684.

Low Load MFII regulating valve Cv, (bypass 48.7 Effective Cv: includes bypass line valves)

MFll Heater resistance (delta p) see HS&L Design data on the High Pressure 0 Heaters (2 in parallel) is provided 3.0 Auxiliary Feedwater (AFM)

Minimus design temperature of the ~ater source 32(*), 50 Initial AFlJ water source are the CSTs service water / CST (degrees F) located in the Service Bldg. Safety Related source is the Service 'Mater system (lake). " Value different for CHMT integrity.

Max'~~ design temperature of the water source 80, 100 initial AFIJ water source arc the CSTs service water / CST (degrees F) 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, *TOAFM starts on LO levet (17K) in sec both gens or UV on both unit HDAFM starts on SI (seq), or 4'usses.

I.O Level either SG, or trip of both HFP or AHSAC Hinimm delay for AFM start, sec TDAF'M - OI HDAFM - 1 HDAFM acceleration time test results show approximately 1.5 s.

Haximua delay for AFM start, sec HDAFM - 47, TOAFM at For HDAFM, LOOP on sequencer is 47 LO Level both SGs sec. TDAFM starts at nominal 17'n both SGs AFM control valve open time on demand, sec H/A HDAFM control valves are normatly open and throttle closed to control flow between 200-230 gpm AFM controL valve Cv[ftow is f(dP)] NDAFMP valves are 3 Rockwell model ¹ A4006JKHY stop check valves. TDAFM controL valves (4297, 4298) are 3 Fisher ¹470-HS.

TDAFMP, maximm flow, gpm 600 AFM, minimus flows, both generators intact, gpm TOAFMP 200/SG SBLOCA assunes 200 gpa per SG with HDAFMP 200/SG the faiture of one DG Hinfmua delay for standby AFM start, min 10 4.0 Hain Stem System (HS)

Location (and elevation) of condenser dump CSD . elev 256'.875 valves and atmospheric relief 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 NSIV - 5.0 The check valve is assuned to close close] close timei sec check vatve - 1.0 in 1 sec under reverse flow.

HS Isolation valve Cv [flow is f (dp)] HSIV - 23500 check valve - 17580 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 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 Number of valves in bank 4 Valve sctpoint(s), (first/last three), nominal, 1085/1140 Valves are Crosby AHA-65 6R10 psig /

Setpoint tolerance Is +1X -3X.

setpoint at 1.01 Nodel valve (nominal), and fuLL flow at 1.04 (nominaL).

VaLve blowdown characteristic 15X max imm 4.2 Atmospheric relief valves No. Atmospheric relief valves 2 Atmospheric relief valve setpoint/Air-operated, 1050 During Hot Standby operation setpoint psig Is lowered to control no load Tavg Atmospheric relief valve setpoint/Booster, psig 1060 Atmospheric relief valve capacity, Lbm/hr 313550 at 1060 psig Nax flow is 380000 5.0 Turbine Generator (TG) 5.1 Condenser No. of condenser disap valves condenser dms valve open time, sec Condenser dms valve close time, sec Assusing close time ~ opening time Condenser dump valve setpoint(s) For TT: Tavg>555 4 valves, Gn TT valves control open at 6.7X/F

>563 4 valves; (PID) above 547 with full open no TT: Tref +12 4 valves, sctpoints as described. On 10X step Tref+20 4 valves Load decrease same ratio with a 6F deadband from Tref Condenser dump vaLve Cv [flow is f(dP)] 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 15 Type of controLLer (e.g., p + 1) and gains PLD 100K,180 sec,10 sec Reactor Hakeup Matei System (QHl)

RHll capacf ty/pulp 2 puris, 60 gpa each 7.0 Emergency Core Cooling System (ECCS) 7.1 ECCS Delivery's RCS Pressure 7.1.1 Residual Heat Removal (RHR) Delivery vs RCS Pressure Hfnfmus RHR Delfvery, train failure RCS Pressure Delivery LOCA Appendix K case. Train failure (psia) (gpm) results fn one punp running with 10K 155 0 degradation with one line bLocked.

152 0 150 0 140 250 120 648 100 836 80 985 60 1115 40 1232 20 1338 14.7 1365 Hfnfaxja RHR Delivery, two fxmys runnfng, one RCS Pressure Delivery LOCA Appendix K case (offsfte power line blocked (psfa) (gpm) availablc). Two pumps running with 155 0 10K 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 (Sf) Delivery vs RCS Prcssure Hfnfmua Si delivery, 2 pumps operating, onc Line Press Delivery Spill LOCA Appendix K case. Train failure spilling (psig) (gpm) (gpm) results in two punps running wfth 5X 1375 0.0 465 degradation with one Line spi llfng to 1300 62 465 contafcment.

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 0 394 465 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 Oelivcry (gpm) Used for non-LOCA transients, 5X pump (psia) Loop I gl

'A'oop degradation 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 Mininnnn Si delivery, 2 pumps operating non-LOCA Press Delivery (gpn) Used for non-LOCA transients, 5X pump (psia) Loop 'A'gl Loop degradation.

1390 8 8 1315 69 71 1215 121 126 1115 162 169 1015 197 206 915 228 239 815 255 269 715 281 296 615 305 322 515 328 346 415 350 369 315 370 391 215 390 412 115 409 432 15 427 452 Maximun Si delivery, 3 punps operating, SGTR Press Loop A Loop 8 The KYPTPE model assunes no pump (psig) (gpn) (gpm) degradation. Loop A and 8 pressures 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 Ac~lators Munster of accunulators 2 Total volune, each, 1750 voluncl ft ft'iquid min/max 1126/1154 Liquid volunei ft - Best Estimate 1140 initial prcssure, psig - Minimun / Maxlmun 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 105 LBLOCA Boron concentration, ppm (mfn/max) 2100/2600 Hote - Ea analyses use a maximus concentratIon of 3000 ppm 7 4 RMST RUST /

TeIIperature, min max, degrees F 60 / 80 fffnfmua RWST votIme, gal 300,000 RMST boron concentration, ppm (min/max) 2300/2600 Hote - EQ analyses use a maxiImm concentration of 3000 ppm 8.0 Contafrment initial contaf~nt pressure p ia min - 14 ' ~ HfnfmuII is used for LOCA analysis.

max - 16.7 Haxfmm is used for the contafwent integrity cases (SI.B).

initial containment temperature (LOCA/SLB) 90/120 LOCA temperature lower for PCT degrees F calculations. SLB hfgher for contairment integrity initial relative huaidity, X 20 SM teIIperature min/max, degrees F 30~/80 *Vatue different for auxiliary feedwater HaxfImm contafment leakage, wtX/day 0.2 8.1 ContafImcnt Heat Sinks Listing of Passive Heat Sinks, quantities, see HSSL metal'fels ~ and configurations 8.2 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 Concrete density, conductivity, capacity 150 ibm/ft note: mfnfImm conductivity 0.81 BTU/hrFf t corresponds to maximus density, and 31.5 BTU/fthm F maxfImm conductivity corresponds to mfnfmun density.

Steel density, conductivfty, capacity 490 tbm/ft 28 BTU/hrFft 54.4 BTU/ft F Stainless steel density, conductfvity, capacfty 496 tbm/ft 15 BTU/hrFft 54.6 BTU/fta F Contafrment free votune, mfn / max, cu. ft. 1,000,000 / 1,066,000 Ground TNIperature (degrees F) 55 below grade temperature Outside Air Temperature, min / max, degrees F -10 / 100 HTC for outside surfaces 1.65 BTU/hr ft degrees F 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 Tenp Hin Hax (deg F) (X106BTU/hr) 120 2.05 4 55 F

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 Contairltent spray flow, min / max, each, gpm 1300 / 1800 8.3 Oclays for CRFCs and Spray punps CRFC delay, offsite power available, seconds 34 includes 2.0 sec SI delay CRFC delay, offsite power not avaf lable, seconds 44 includes 2.0 sec SI delay Contafnment Spray, 1300 gpm each fxlp, maxfmun 28.5 - onc punp This delay is from the tfme delay, sec 26.8 - two pumps Containment Hi-Mi setpoint is reached. It includes instrunent delay and spray line fill time.

Contafreent Spray, 1800 gpm each punp, mfnfmun 9 / (14 w LoOP) This delay is from the tfme of break.

dele/, sec ContafrInent Oesfgn pressure, psig 60 Ofstance Basement floor to Springline, feet 95 Oistance Sprfngline to top of done, feet 52.5 8.4 Contairwent Surp Hinimun wtX of HaOH Tank 30 9.0 Control Systems (Reactor, FM, przr Level, Turbine, AFIJ)

Tavg versus power H/A Tavg ramps Linearly from 547 degrees F at OX power to 561 degrees F at 100K power pressurizer pressure and level algorithms N/A pressurizer pressure setpoint is constant at 2235 psig . Pressurizer leveL reaps from 35K to 50K for 0 to 100K power (547 - 561 degrees F).

SO secondary level algorithm H/A Level remains constant at 52X to 100X power. (Power from turbine 1st stage press.)

10.0 Sa fcty System Setpoints 10.'I Reactor Protection System 10 ~ 1.1 power range high neutron flux, high setting nominal 1.09 accident analysis 1.18 delay time, sec 0.5 10.1.2 Power range high neutron flux, Low setting nominal 0.250 accident analysis 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 Variable accident analysis Variable delay time, sec 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 Variable accident analysis Variable Hot explicitly modelled in safety analysis delay time, sec 2.0 10.1.5 High pressurizer pressure nominal, psig accident analysis, psia 2410 delay time, sec 2.0 10.1.6 Low pressurizer pressure nominal, psig 1873 accident analysis, psia 1775 (non-LOCA) 1715 (LOCA) 1905 (SGTR) delay time, sec 2.0 10.1.7 Low reactor coolant flow nominal 91K of normal indicated flow accident analysis 87X per Loop delay time, sec 1.0 10.1.8 Low-Low SG level nominal 17K of the narrow range While trip setpoint could be as Low Level span as 16K, AFll initiation Limits to 17K accident analysis OX of narrow range Level span delay time, sec 2.0 10.1.9 Turbine Trip (low fluid oil pressure) nominal, psig 45 accident analysis H/A Hot explicitly modeled in safety analysis delay time, sec 2.0 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 3150 accident analysis Safety analysis assunes RCCAs are released 1.5 scc. after sctpoint is released.

delay time. sec 1 ~ 5 10.1.11 Undcrfrcqumcy nominal, Hz 57.7 accident analysis 57.0 Analysis is performed but not explicitly modeled in safety analysis.

delay time 1.2 Safety analysis assunes RCCAs are released 1 ' sec after setpoint is reached.

10.1.12 Intermediate range nominal, RTP 0.25 Hay fluctuate duc to core flux safety analysis, RTP H/A Hot explicitly modeled in safety'nalysis delay time, sec H/A 10.1.13 Source Range nominal, cps 1.4E+5 Highest nominal value accident analysis, cps 1 AL OE+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 Englneercd Safety Features Actuation System 10.2.1 Sa fcty injection System 10.2.1.1 'High con'tailNcAt prcssure Hominal setpoint, psig 4.0 Accident Analysis setpoint, psig 6.0 * *only modeled in accident analysis for start of containment fan coolers.

oelay time, sec 34 Time delays are for start of 44 w/ LOOP containment fan coolers.

10.2.1.2 Lou pressurizer pressure Hominal setpoint, psig 1750 COLR 23 Cycle 27, Revision 0

Table 1:

Xtem 4 UFSAR

~

Xtem/Name Chapter 15 Analysis Setpoints and input parameters Value

~

Remarks:

Accident Analysis setpoint, psia 1785, SGTR 1730, non-LOCA 1715, LOCA Delay time, sec 2.0 10 2.1 3 Low ate~ line pressul e Hominal setpolnt, psig 514 Accident Analysis setpoint, psig 372.7 See HS&L Delay time, sec 2.0 See NS&L 10.2.2 Contairwmt Spray Hominal Setpoint, psig 28 Accident analysis setpoint, psig 32.5 Sec HS&L Delay time, sec 28.5 Delay time includes time to fill lines. See HS&L 10.2.3 AFM System Lcw low ate~ generator water Nominal Setpoint 17 X of narrow range instrunent span each steam generator Accident analysis setpoint 0 X of narrow range A positive 11K error has been instrunent span each steam included to account for the SG level generator measurement system at a contairraent tecperature of 286 F Delay time, sec 2.0 10.2 4 Steam Line Isolation 10.2.4.1 High conte irsaent 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 Hominal Sctpoint 0.4E6 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 power Accident analysis setpoint N/A Not explicitly modeled Delay time N/A 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 3.6E6 lb/hr equivalent steam flow at 755 psig Accident analysis setpoint 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 Hominal Setpoint 85X of the narrow range instrunent span each SG Accident analysis setpoint 100X of the narrow range instrunent span each SG Delay time 2.0 Lnstrunent loop only 11 0 Bill Stem Generators Heat load per SG, BTU/hr 2,602,000,000 Primary flow per SG, Klb/hr PluggingX 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 teaperature, F 556 Maxicxla moisture carryover, X 0.10 Harrow range level tap secondary face locations, inches above 386/s / 529/I TS Mide range level tap Locat'ions, inches above TS secondary face 8 /~ / 529 /e SG Pressure Drops Secondary nozzle to nozzle dP Q full power, psi 14.7 Value is totaL static pressure drop.

Secondary nozzle to nozzle dP Q full po~er, psi 7.5 Pressure drop from top of U-bend to outlet.

primary nozzle to nozzle unrecoverable pressure PluggingX ap psi See associated flows for X plugging.

cirop vs. plugging, psi 0 31.01 5 33.27 10 35.82 15 38.72 11.2 SG Tubes Ho. of tubes per SG 4765 Tube 00, inches 0.750 Tube average wall thickness inches 0.043 Maxinxla tube length, ft 70.200 Includes length in tubesheet (2x25.625")

Minimus 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 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 3.979 Note: this is not the bend radius for the shortest tube.

Haxiaam 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 /lg / 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 Neat BTU/lb.F Temp F Conductivity 200 0.112 300 0. 1155 400 0.119 500 0.1225 600 0.126 Distance from top of tube bundle to fthm 33'RL, ft 5.703 11.3 SG Voltmes 11.3.1 SG Secondary Side Vol~

secondary volte, ft (total) 4512.7 Secondary volune up to lower NRL tap, ft 1893.2 Secondary volune up to upper NRL tap, ft 3460.4 11.3.2 Riser Volmes ft'281.8 Secondary side bundle volune (TS to top of U-bend inside shroud),

secondary riser volune, top of U-bend to spill- 507.0 Equivalent to LOFTRAN riser volune.

ft'59.6 over point, 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 1437.3 point, 11.3.4 SG Primary Side Valuate Inlet plenua per SG, fts 129.65 Outlet plenun per SG, fthm 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 710.3 Primary total volune per SG, fthm 969.6 Circulation ratio (100X power, clean, unplugged) 5.39 Circulation ratio = bundle flow g steam flow. Assunes 40,000 Lbmghr b lowdown.

Tubesheet thickness, inches 25.625 Includes cladding.

11.4 SG Primry Side Dimensions PHmary head radius, inches 58.375 Radius to clad surface.

Divider plate thickness, inches 1.875 Inlet and outlet nozzle, inside diametel 31.200 cylindrical section, inches Nozzle divergence angle, degrees 11 30'7.0 Nozzle inside diameter at plena, inches Nozzle Lengths, inches cylindrical section 8.75 conical section 13.0 total length 21.75 Heigth from SG primary head bottom (outside) to 90'lle top of Ts, inches Distance tube sheet primary face to hot leg 6.654 centerline, ft.

11.5 SG Secondary Side Dimensions Lower shell inside diameter, inches 122 Lower 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 flow restricter area, 1.4 secondary face of TS to centerline of ft'istance 407'i, feedwater 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 DSG.

Primary side roughness, micro-inches Hozzles, head 60 values given are conservative Tubes 60 assunptions.

SG Secondary Side Mater Hasses Secondary ~ater inventory, 100)', power, T,, ~ 86,259 liquid gest estimate value.

573.5, no plugging, ibm 5,286 steam Secondary water inventory, 100'ower, T, 85,547 liquid gest estimate value.

559, no plugging, Lbn 4,675 steam 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 1.01E-09 for ID <<31.2<<

gG outlet nozzle/plenum loss coefficient, 3.31E-10 for IO <<31.2<<

ft/gpm gG tubing loss coefficient, ft/gpm 9.62E-09 for OX plugging For cube ID <<0.664", Ao>> <<11.458 1.32E-08 for 15X plugging fC2~ A~~>>

assumed to be uniform.

SG Cubing loss coefficient, sCraight section 4.19E-09 for OX plugging For tube ID << 0.664<<, A << 11.458 (in), ft/gpm'G 5.73E-09 for 15K plugging ft, A,~>> "-9.739 ft .

assuned to be uniform.

Plugging is tubing loss coefficient, U-bend section, 1.02E-09 for OX plugging For tube 10 = 0.664", Ao>> = 11.458 ft/gpm 1.40E-09 for 15K plugging fc', A= 9.739 ft . Plugging is assumed to be uniform.

$0 tubing Loss coefficient, straight section 4.41E.09 for OX plugging For tube ID = 0.664" ~ Ao" -11.458 (out), ft/gpm 6.08E-09 for 15X plugging fthm, Al5>> = 9.739 ft2. Plugging is assumed to be uniform.

COLR 28 Cycle 27, Revision 0

4