ML17264A401

Rev 0 to COLR Cycle 25.

ML17264A401
Person / Time
Site:	Ginna
Issue date:	02/24/1996
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264A399	List: ML17264A398 ML17264A400 ML17264A401
References
NUDOCS 9603140438
Download: ML17264A401 (29)

Text

COLR GINNA STATION Cycle 25 Revision 0 CORE OPERATING LIMITS REPORT .

{COLR)

Res onsible Hanager Effective Date Controlled Copy Ho.

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05000244 PDR ADQCK

R.E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 25 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 LIMITS REPORT ....... -....... 2 3

2.1 SHUTDOWN MARGIN . 3.

3' 2.2 MODERATOR TEMPERATURE COEFFICIENT .

2.3 Shutdown Bank Insertion Limit .

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"~)

2.7 AXIAL FLUX DIFFERENCE . ~ ~ 4 2.8 RCS Pressure, Temperature, and Flow Departure from Nucl cate Boiling (DNB) Limits 5 2.9 Boron Concentration . 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 . 10 TABLE 1 - UFSAR CHAPTER 15 ANALYSIS SETPOINTS AND INPUT PARAMETERS..... 11 COLR Cycle 25, Revision 0

RE E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 25 Revision 0 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, T~emperature, and Flow Departure from Nucleate Boiling (DNB) Limits" 3.9.1 "Boron Concentration" COLR Cycle 25, 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 l.

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 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 ~ 222 steps.

COLR Cycle 25, 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

F (Z) s ~F g"K(Z) when P ~ 0.5

0.5 where

Z is the height in the core, Fo = 2.32, K(Z) is provided in Figure 3, and THERMAL POWER P = RATED THERMAL POWER 2.6 Nuclear Enthal Rise Hot Channel Factor F" J (LCO 3.2.2)

(Limits generated using Reference 1) 2.6.1 F" s F" * (1 + PF * (1-P))

ATP where: F 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 prov'ided by Procedure RE-11. 1.

2.7.2 The AFD acceptable operation limits are provided in Figure 4.

COLR .

Cycle 25, Revision 0

2.8 RCS Pressure Tem erature and Flow De arture from Nucleate Boilin Li (L (Limits generated using Reference 4) 2.8.1 The pressurizer pressure shall be a 2205 psig.

2.8.2 The RCS average temperature shall be ( 577.5 F.

2.8.3 The RCS total flow rate shall be a 170,200 gpm.

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 a 2000 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 Main 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 25,'evision 0

4.0 REFERENCES

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

2. WCAP-9220-P-A, Westinghouse ECCS Evaluation Hodel-1981 Version, Rev. 1, February 1982.

OR WCAP-10054-P-A and WCAP-10081, "Westinghouse Small Break ECCS Evaluation Hodel Using the NOTRUHP 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 Questions," December 1988.

WCAP-10924-P, Volume 1, Rev. 1, Addendum 4, "Westinghouse LBLOCA Best Estimate Methodology; Hodel Description and Validation;'Model Revisions," August 1990.

3. WCAP-8395, "Power Distribution Control and Load Following Procedures Topical Report," September 1974.

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

5. WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988.

COLR Cycle 25, Revision 0

3 ONE LOOP (0,2AS)

ACCEPTABLE OPERATION Cl tU 2 Cf (0, 1 CL %NO LOOP (1600, 1A5) OP ERA'nON g1 (1500, 1lN)

UNACCEPTABLE OPERATION 0

0 1500 1000 500 COOLANT BORON CONCENTRATION (ppm)

FIGURE I REQUIRED SHUTDOWN MARGIN COLR Cycle 25, Revision 0

~ 220 ddd, I> 200 8 Bank 2 180 Q 160 C Bank

~ $ 40 B 120 OB o )00 o 80 60 ca 40 o 20 0

0 10 20 30 40 50 60. 70 80 90 'f00 Core Power (Percent of 1520 MNIT)

The fully withdrawn position is defined as ~222 steps.

FIGURE 2 CONTROL BANK INSERTION LIHITS COLR Cycle 25, Revision 0

0.75 Total Fq = 2.320 Core Height K(Z) 0.00 1.000 6.00 $ .000 0.25 10.80 0.940

$ 2.00 0.647 0

a 4 6 8 CORE HE}GHT (ft}

FIGURE 3 K(Z) - NORMALIZEO Fo(Z) AS A FUNCTION OF CORE HEIGHT COLR Cycle ZS, Revision 0

DO NOT OP ERA1% IN THIS AREA iIVITHAFD OUTSIDE THE TARGET SANO

(-1 $ ,90) (<180) 80 ACCEPTABLE OPERAT lON NlfH AFD OUTS GE THE TARGET 8AN9 NITHcf HR PENALTY 0 60 DEMATION ThlE (44,60) P1/0) lL 40 ACCEPTABLE OP ERATION 20 0

<0 -20 -10 0 50 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 25, Revision 0

Table 1: UFSAR Chapter 15 Analysis Setpoints and Xnput Parameters Xtem g Xtem/Name Value Remarks:

1.0 Reactor Coolant System (RCS)

Upper head volune, ftn 300.0 Above upper support plate.

Upper Plenun volune, 580.2 Bottom of upper core plate to top of upper support plate. Includes outlet ft'op holes in the barrel.

of fuel volune, ft 50.3 Top of active fuel to bottom of upper core plate, inside barrel baffle.

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 votune.

Active fucL voLune, 367.6 Bottom of fuel to top of fuel Bottom of fuel volunc, ft 11 ~ 0 Top of lower core plate to bottom of active fuel.

Lower Plenun volune, ft 514.3 Below top of lower core plate Downcomer volune, above bottom of cold leg, ft 138.4 Above bottom of cold leg clcvation to bottom of upper support plate Oowncomer, lower core plate to elevation of thc 278.2 Top of lower core plate to elevation bottom of the cold lcg volunc, ft of bottom of cold leg Barrel baffle, lower core plate to upper ccrc 128.5 Top of lower core plate to bottom of plate volune, ftn upper core plate.

Total volunc, 2449.1 Includes nozzles ft'ot lcg pipe volune per loop volune, ftn 78.7 Cold lcg volune per loop + cross over, ftn cross over ~ 140.7 cold Lcg = 46.8 RC pump volune per pump, ft 192 Cold leg pipe ID, in. /Pump suction IO, in. 27.5/31 Hot lcg pipe ID, in. 29 (28.969)

Design prcssure, psig 2485 Design tenperature, F 650 Cold Lcg and Hot Leg Centerline ELevation 246'0" Reactor Coolant Pmp Head-Capacity and HPSH curves for reactor See HSILL Homologous Curves are available in cooLant pumps/Homologous Curves RETRAH Rated RC punp head and flow, ft 8 gpm 252; 90,000 Rated RC punp torque and cfficicncy Q rated 84y. efficiency at hot head/flow, ft-lb, fraction conditions RCP Pump Rated Power (hot, 556 dcgrces F) 4842 BKP RCP Hotor Rated Speed, RPH 1189 Homent of inertia of pump and motor, lb-ft 80,000 COLR Cycle 25, Revision 0

Table 1: VFSAR Chapter 15 Analysis Setpoints and Xnput Parameters Xtem 4 Xtem/Name Value Remarks:

-RC pump power, HMt (max/min) 10, 8 Purp power varies with RCS tarp from approx 8 KMt to 10 HMt 1.2 Core Rated power, IQt 1520 Reactor power uw:ertainty, )! RTP Bypass, )! 4.5 Thimble plugs removed.

Upper head bypass, )( LI proprietary Upper head tcaperature, degrees F 590 Heat transfer area, ft 26,669 Average core heat flux, Btu/hr-ft* 189,440 1.3 Fuel Assanbties 1.3.1 Height Total, inches (length from bottom of assarbty to 159.935 top nozzle)

Fuel Rod Length, inches (length fran bottom of 149.138 pin to top of pin)

Active, inches 141.4 Fuel Assarbty Geanetry Hoss of fuel, tbm 105,500 Hass of clad, ibm 25,927 Hunber of fuct pins per fuel assarbty (FA) 179 Ho. of Fuel Assarblies 121 Fuel pin pitch, in. 0.556 Bottom nozzle weight and volune 9.1 lbs.

31.5 in'8.15 Top nozzle, w/ insert, weight and votune lbs.

62.9 in'ore Fuel Assembty resistance (core dP f(flow)], psi delta P n 20 psi Thimbte plugs removed.

f(tb/hr) 9 flow = 170,200 gpm Fuel Asscnbty frcc flow area, inn 34.75 SingLe assarbly 1.3.3 Fuel pin geometry Pcltet diamctcr, in. 0.3444 Clad 00/IO, in. /in. 0.400/0.3514 1.3.4 Control Rod B Instruncnt Guide Tubes Ho. of control rod guide tubes 16 Ho. of instruncnt guide tubes Control Rod Guide tube upper part 00/IO, in./in. 0.49/0.528 instruncnt Guide tube OD/IO, in./in. 0.395/0.350 Guide tube lower part OD/ID, in./in. 0.4445/0.4825 COLR 12 Cycle 25, Revision 0

Table 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters

( Xtem g Item/Name Value Remarks:

Control Rod Drop Times, maximuns, sec. Hon-LOCA 2.4 Allowances arc added to the Tech Spec LOCA 3.0 allowable value.

Control rod maxiaxxa withdrawal rate, in./min. 45 Control rod maximua insertion rate, pcm/scc. 90 Control rod insertion limits Sce COLR Hot channel radial peaking factor 1.66 Heat Flux Kot channel factor FQ 2.32 1.4 Pressurizer Code safety valve flow capacity, ibm/hr 288,000 Rating at 2485 psig plus 3X accunulation 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 number 2 Spray valve flow capacity, gpn/valve 200 Spray valve setpoint- start open/full open 2260/2310 Proportional Spray valve time constant, sec. 5 Assumed value PORV nunber 2 PORV flow capacity, ibm/hr .179,000 Steam flow at 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 E11CH-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 E11CH-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 sctpoint [LTOP] open/close, psig 430 PORV blowdown characteristic Heater capacity w/ bank capacity and sctpoints, 800 kW Control banks 0 kW at 2250 psig and 400 kW at 2220 psig Backup Heaters Full on at 2210 psig and resets at 2220 psig Hinimua hcatcr capacity required for LOOP, kW 100 Kcatcr bank controller type proportional 400 kW 1.4.1 Pressurizer voluae(s) (100X / OX power)

Water, ft (100X / OX power) 396/199 Steam, ft (100X / OX power) 404/601 Total, ft 800 COLR 13 Cycle 25, Revision 0

Table 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters

( Item Item/Name Value Remarks:

Pressurizer ID, ft-in 83.624 in / cladding thickness is 0.188 in Surge linc ID, in. 8.75. Surge line is 10 in schedule 140 Spray line ID, in. 3.062 Surge line voiure, ft 18.4 1 4.2 Pressurizer Level Lower level tap elevation 257' Upper level tap elevation 275' Pressurizer level vs X power Xpower Level Pressurizer level is rampcd linearly 0 X 19.5X bctwecn these points.

100 X 49X Distance Hot Lcg Centerline to Lower Tap, ft 10.750 Haximm 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, gpm (15X plugging) 173,800 Use for statistical DHB Average reactor coolant tettperature, degrccs F 573.5/547 (Full power/HZP)

Reactor coolant prcssure, psig 2235 Reactor coolant flow uncertainty, X nominal 3.1 Reactor coolant temperature uncertainty, degrccs F

Reactor coolant prcssure uncertainty, psi a 30 DHB Limit (safety analysis) 1.52 typical cell 1.51 thimble cell 1.6 Low Tesperaturc Ovcrpressurc Protection (LTOP)

Hinimua RCS vent size, square inches Ho. of SI pumps capable of injection 0/1 (PORVs/vent)

Haximua pressurizer level for RCP start, X 38 1.7 Fuel Handling/Dose Calculations Maxiaxln reactor coolant gross specific activity 100/E pCi/gm Haximun reactor coolant dose equivalent I-131 ~ 1.0 pCi/gm Haximua secondary coolant dose equivalent I-131 0.1 pCI/gm Hinimm reactor coolant boron concentration, ppm 2000 Hininxm reactor coolant level 23 ft above flange Hiniaxia spent fuel pool level 23 ft above fuel Kinlaam spent fuel pool boron concentration, ppm 300 Spent fuel pool tecpcrature, degrees F (min/max) 50/180 Hinimla spent fuel pool charcoal filter 90 efficiency, X methyl iodine removal COLR 14 Cycle 25, Revision 0

Table 1: UFSAR Chapter 15 Analysis Setpoints and Xnput Parameters

( Xtem g Xtem/Name Value Remarks:

Hinimm post accident charcoal filter 90 efficiency, X methyl iodine removal Ninisxln control room charcoal filter efficiency, 90 X methyl iodine removal Hininua time between reactor criticality and 100 fuel movement, hrs.

Source Terms used for dose calculations TIO 14844, WCAP-7823 Haximm Gas Oecay Tank Xenon-133 concentration, 100,000.

Ci 2.0 Nain Fecdwater (NRI)

Fecdwatcr tceperaturc versus load Power Temperature 100X design temp is 432 dcgrces F 102X 425 F 70X 385 F 30X 322 F OX 100 F Feedwater Suction Tecperature vs Power, nominal Power Tempcraturc 98X 345 F 70X 319 F 50X 295 F 30X 259 F Fcedwatcr Suction Pressure vs Power, nominal Power Pressure 98X 277 psig 70X 282 psig 50X 305 psig 30X 370 psig 2.1 Head-Capacity and NPSN curves Head-Capacity and NPSN curves for main fecdwater See NSILL Selected flow splits are provided for IxmlPS model validation.

Hain Fccdwater pmp - Rated Head Nain Fcedwatcr pmp - Rated Torque 2150'89.612 Nain Fecdwatcr purp - Nomcnt of Inertia ELevation of steam generator inlet nozzle Elevation of main feedwatcr pump, ft 257.75 Elevation is at center of shaft Elevation of condensatc punp, ft 250.833 HFW regulating valve open time on demand, scc HFW regulating valve close time on demand, sec 10 HFW transients use 20 scc stroke time HFW regulating valve Cv, full stroke 990 Assuaed vaLue. Actual value " -493.6.

Low load NFW regulating valve Cv, (bypass 48.7 Effective Cv: includes bypass line valves)

HFW Neater rcsistancc (delta P) see NS8L Oesign data on the Nigh Pressure Heaters (2 in parallel) is provided 3.0 Auxiliary Fccdwatcr (ARI)

Ninimm design tccperature of thc water source 32(+), 50 Initial AFW water source are the CSTs se'rvicc water / CST (degrees F) located in the Service Bldg. Safety Related source is thc Service Water system (lake).

• Value different for CNHT integrity.

Haximrn design tcaperaturc of the water source 80, 100 Initial AFW water source are thc CSTs service water / CST (degrees F) located in the Service Bldg. Safety Related source is thc Service Water system (lake).

COLR Cycle 25, Revision 0

Table 1: UFSAR Chapter 15 Analysis Setpoints. and input Parameters

'I item 4 Xtem/Name Ualue Remarks:

Startup time for thc auxiliary fecdwater pumps, *TDAFM starts on LO level (17X) in sec both gens or UV on both unit 4Kv busses. HOAFM starts on SI (seq), or LO level either SG, or trip of both HFP or AHSAC Hininxrn delay for AFM start, sec TOAFM - 0, HOAFM - 1 HOAFM acceleration time test results show approximately 1.5 s.

Haximm delay for AFM start, sec HOAF'M - 47, TOAFM at For HDAFM, LOOP on sequencer is 47 LO Level both SGs sec. TOAFM starts at nominal 17X in both SGs AFM control valve open time on demand, scc N/A HOAFM control valves are normalLy open and throttle closed to control flow between 200-230 gpm AFM control valve Cv(flow is f(dP)] HOAFMP valves are 3 Rockwell model g A4006JKHY stop check valves. TOAF'M control valves (4297, 4298) are 3 Fisher 0470-NS.

TDAFMP, maximun flow, gpm 600 AFM, minimus flows, both generators intact, gpn TOAFMP 200/SG SBLOCA assunes 300 gpm pcr SG with HOAFMP 200/SG the failure of onc DG Hinimun delay for standby AFM start, min 10 4.0 Hain Ste~ System (HS)

Location (and elevation) of condenser dunp CSO - elcv 256'.875 valves and atmospheric relief valves ARV - elev 289'.563 Full load stcam line pressure drop, psi approx 45 This estimate, to the governor valves, is provided for cocparison purposes only.

HS Isolation valve close time (full open to full HSIV - 5.0 Thc check valve is assumed to close close] close time, sec check valve - 1.0 in 1 scc under revcrsc flow.

HS Isolation valve Cv (flow is f(dP)] HSIV - 23500 check valve - 17580 4.1 Hain Stoma Code Safety Valves Number of valves (4 pcr Line) 8 Valve flow capacities - Total, ibm/hr 6621000 Rated flow (3X accunulation per ASHE,Section III):

1085 psig ~ .... ~ .......... 797,700 ibm/hr (each) 1140 psig ~ ...... . .. ... 837,600

~ ~ ~ ~

ibm/hr (each)

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 COLR l6 Cycle 25, Revision 0

Table 1: VFSAR Chapter- 15 Analysis Setpoints and Input Parameters

{ Item g Item/Name Value Remarks:

Nurbcr of valves in bank 4 Valve setpoint(s), (first/last three), nominaL, 1085/1140 Valves are Crosby ¹HA-65 6R10 ps ig /

Setpoint tolerance is +1X -3X.

Model valve setpoint at 1.01 (nominal), and full flow at 1.04 (nominal).

Valve blowdown characteristic 15X max i sun 4.2 Atmospheric relief valves No. Atmospheric relief valves 2 Atmospheric rclicf valve sctpoint/Air-operated, 1050 During Hot Standby operation sctpoint psig is lowered to controL no load Tavg Atmospheric relief valve sctpoint/Booster, psig 1060 Atmospheric relief valve capacity, ibm/hr 313550 at 1060 ps ig Max flow is 380000 5.0 Turbine Generator (TG) 5.1 Condenser No. of condenser dutp valves Condenser dump valve open time, scc Condenser dump valve close time, sec Assuaing close time " -opening time Condenser chmp valve setpoint(s) For TT: Tavg>555 4 valves, On TT valves control open at 6.7X/F

>563 4 valves; (PID) above 547 with 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 dump valve Cv (flow is f(dP)) Design Cv (240) from design conditions (302,500 ibm/hr sat steam at 695 psig) 6.0 Chemical and Voluac Control System (CVCS)

CVCS capaci ty/pump 3 pumps, 60 gpm max each Normal ops: 2 charging pumps - onc is manuaL at 15-20 gpm and the other in automatic. Charging ixmps are PDPs w/ 46 gpm total - 8 gpm to seals - 3 gpm leakage + 5 gpm into RCS. 40 gpn letdown CVCS minimumlpump, gixa 15 Type of controller (c.g., P + l) and gains PLD 100X,180 sec,10 sec 6.1 Reactor Makeup Mater System (RMM)

RKM capacity/pwp 2 pumps, 60 gpa 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 COLR 17 Cycle 25, Revision 0

v ~

Table 1: UFSAR Chapter 15 Analysis Setpoints and Xnput Parameters item g Xtem/Name Value Remarks:

Hinimm RRR Delivery, train failure RCS Pressure Delivery LOCA Appendix K case. Train failure (psia) (gpm) results in one pump 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 Hiniaun RHR Dclivcry, two punps running, one RCS Pressure Dclivcry LOCA Appendix K case (offsitc power linc blocked (psia) (gpm) available). Two pumps running with 155 0 10K degradation, with onc 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) Dclivcry,vs RCS Pressure Hininxsn Sl dclivcry, 2 pumps operating, one linc Press Delivery Spill LOCA Appendix K case. Train failure spilling (psig) (gpa) (gpm) results in two pumps running with SX 1375 0.0 465 degradation with one line spilling to "1300 62 465 contaiwent.

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 Hinimm Si delivery, 3 pumps operating, non-LOCA Press Delivery (gpm) Used for non-LOCA transients, 5X pump (psia) Loop 'A'oop degradation Igl 1390 16 19 1315 87 97 1215 147 163 1115 193 214 1015 231 257 915 815 715 266 297 325

'29 295 360 615 352 390 515 377 418 415 400 444 315 423 469 215 445 493 115 465 516 15 485 538 COLR 18 Cycle 25, Revision 0

'V ~

lO Table 1: UFSAR Chapter 15 Analysis Setpoints and Xnput Parameters

( Xtem g Xtem/Name Value Remarks:

Kininun Si delivery, 2 pimps operating non-LOCA Press ,Delivery (gpm) Used for non-LOCA transients, 5X pwp (psia) Loop 'A'BI 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 KaxisxIa SI dclivcry, 3 punps operating, SGTR Press Loop A Loop B The KYPIPE model assuncs no pump (psig) (gpa) (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 BOO 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 COLR 19 Cycle 25, Revision 0

1: Chapter 15 Analysis Setpoints and Xnput Parameters lN'able UPSAR Xtem g Xtem/Name Value Remarks:

7.3 Acct' ate ra Naker of accunulators 2 Total velum, each, ft 1750 Liquid votune, ft' min/max 1126/1154 Liquid voiune, ft - Best Estimate 1140 Initial prcssure, psig - Hininun / Haxlmua 700/790 Initial tccperature, F 105 LBLOCA Boron concentration, ppm (min/max) 1800/2600 Note - EQ analyses use a maxinxm concentration of 3000 ppm 7.4 RMST /

Tecperature, min max, degrees F 60 / 80 Hinimxn RNST volunc, gal 300,000 RNST boron concentration, ppm (min/max) 2000/2600 Note - EQ analyses use a maximua concentration of 3000 ppm 8.0 Contaireent Initial containment pressure, psia min - 14.5 Hiniaun is used for LOCA analysis.

max - 15.7 Haximun is used for the containment integrity cases (SLB).

Initial contaireent tenperaturc (LOCA/SLB) 90/120 LOCA temperature lower for PCT degrees F calculations. SLB higher for containment integrity Initial relative humidity, )l 20 SM tettperature min/max, degrees F 35/80 Haximun contaiment leakage, wtX/day 0.2 81 Contairment Neat Sinks Listing of Passive Neat Sinks, quantities, see NSSL materials, and configurations 8.2 Dcnsitics, Thermal Conductivitics and Neat Capacities of Neat Sinks Insulation density, conductivity, capacity 6.67.ibm/ft 0.0208 BTU/hr F ft 2.0 BTU/ft F 141 ibm/fta to 150 lbm/fta note: minimun conductivity 0.73 to 0.81 BTU/hrFft corresponds to maximm density, and 0.21 BTU/ibm F maxinua conductivity corresponds to minimxn.density.

Stccl density, conductivity, capacity 490 ibm/ft 28 to 30 8'IU/hrFft 0.111 BTU/ibm F Stainless steel density, conductivity, capacity 496 ibm/ft 15 BTU/hrFft 0.11 B'IU/ibm F Containment free volune, min / max, cu. ft. 1,000,000 / 1,066,000 Ground Temperature (degrees F) 55 below grade tettperature Outside Air Temperature, min / max, dcgrces F -10 / 100 COLR 20 Cycle 25, Revision 0

Table 1: VFSAR 0Chapter 15 Analysis Setpoints and Input Parameters

( Item g Item/Name Value Remarks:

HTC for outside surfaces 1.65 BTU/hr fta degrees F Contairaent fan cooler performance Tcap Hin Hax (dcg F) (X106BTU/hr) 120 2.05 4.55 220 35.1 99.2 240 40.8 113.8 260 46.8 129.3 280 52.9 145.5 286 54.7 150.4 Contairment spray flow , min / max, each, gpm 1300 / 1800 8.3 Delays for CRFCs and Spray Pcs CRFC delay, offsite power avaiLable, seconds 34 includes 2.0 sec SI delay CRFC delay, offsitc power not available, seconds includes 2.0 sec Sl delay Contairaent Spray, 1300 gpm each pump, maxiaaia 28.5 - one lxlp This delay is from thc time delay, sec 26.8 - two pumps Contairaent Hi-Hi setpoint is reached. It incLudes instrunent delay and spray linc fill time.

Contairmcnt Spray, 1800 gpm each pip, minicua 9 / (14 w LOOP) This delay is from the time of break.

delay, sec Containnent Design pressure, psig 60 Distance Basement floor to Springline, feet 95 Distance Springline to top of dome, fcct 52.5 8.4 Contairmcnt Suap Hinimua wtX of NaOK Tank 30 9.0 Control Systems (Reactor, FM, Przr Level, Turbine, AFN)

Tavg versus power N/A Tavg ramps linearly from 547 degrees F at OX power to 573.5 degrees F at 100X power Pressurizer pressure and level algorithms N/A Pressurizer prcssure sctpoint is constant at 2235 psig Pressurizer

~

lcvcl ramps from 19.5 X to 49X for 0 to 100 X power (547 - 573.5 dcgrces F).

SG secondary Level algorithm N/A Level rasps from 39X at OX power to 52X at 20X power and remains constant at 52X to 100X power. (Power from turbine 1st stage press.)

10.0 Safety System Sctpoints 10.1 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 COLR 21 Cycle 25, Revision 0

~ v Table 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters

( Item g Item/Name Value Remarks:

accident analysis 0.350 delay time, scc 0.5 10 1.3 Overtaaperature delta T nominal Variable accident analysis Variable delay time, sec 6.0 Total delay time - from the time the tenperaturc difference in the coolant loops exceeds the trip setpoint until the rods are free to fall 10.1.4 Overpower delta T nominal Variable accident analysis Variable Not explicitly modcllcd in safety analysIs delay time, sec 2.0 10.1.5 High pressurizer pressure nofninal ~ psig accident analysis, psia 2410 delay time, scc 2.0 C

10.1.6 Lou pressurizer prcssure nominal, psig 1873 accident analysis, psia 1775 (non-LOCA) 1715 (LOCA) 1905 (SGTR) delay time, sec 2.0 10.1 7 Lou reactor coolant flow nomina l 91X of normal indicated flow accident analysis 87X per loop delay time, sec 1.0 10.1.8 Lou-lou SG level nominal 17X of thc narrou range Mhile trip sctpoint could bc as low level span as 16X, AFW 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) nominal, psig 45 accident analysis N/A Not explicitly modeled in safety ann lys'I s delay time, scc 2.0 COLR 22 Cycle 25, Revision 0

Table 1: UPSAR Chapter 15 Analysis Setpoints and Xnput Parameters

( Xtem g Xtem/Name Value Remarks:

10 1 10 Undervoltagc nominal, 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 Underfrectuency 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 arc released 1.2 sec after sctpoint is reached.

10.1.12 Intermediate range nominal, RTP 0.25 Hay fluctuate due to core flux safety analysis, RTP H/A Hot explicitly modclcd in safety analysis delay time, sec N/A 10.1.13 Source Range nominal, cps 1.4E+5 Highest nominal value accident analysis, cps 1.0E+5 delay time, sec 2.0 10.1.14 High Prcssurizcr level nominal 0.90 accident analysis 0.938 delay time, sec 2.0 10.2 Enginccrcd Safety Features Actuation System 10.2.1 Safety Injection System 10.2.1 1 High contairelent pressure Nominal setpoint, psig 4.0 Accident Analysis setpoint, psig 6.0 * *only modeled in accident analysis for start .of contaireent fan coolers.

Delay time, scc 34 Time delays arc for start of 44 u/ LOOP contaiwent fan coolers.

10.2.1.2 'Lou pressurizer prcssure Nominal setpoint, psig 1750 Accident Analysis setpoint, psia 1785, SGTR 1730, non-LOCA 1715, LOCA Delay time, sec 2.0 COLR 23 Cycle 25, Revision 0

'A Table 1: UFSAR Chapter 15 Analysis Setpoints and Input Parameters

( Item 4 Item/Name . Value Remarks:

10.2.1.3 Low steam linc pressure Nominal setpoint, psig 514 Accident Analysis setpoint, psig 372.7 Sec NS&L Delay time, sec 2.0 See NS&L 10.2.2 Contairwcnt Spray Nominal Setpoint, psig 28 Accident analysis setpoint, psig 32.5 Sec NS&L Delay time, sec 28.5 Delay tine includes time to fill lines. See HS&L 10.2.3 AFM System Low-low st~ generator water level Hominal Sctpoint 17 X of narrow range instrunent span each stcam generator Accident analysis setpoint 0 X of narrow range A positive 11K error has been instruaent span each stcam included to account for thc SG level generator measurement system at a containment temperature of 286 F Delay time, scc 2.0 10.2.4 Stems Linc Isolation 10.2.4 1 High contairioent pressure Hominal Setpoint, psig 18 Accident analysis setpoint N/A Hot explicitly modeled Delay time N/A Not explicitly modeled

'10.2.4.2 iiigh steam flow, coincident with low Tavg and SI Nominal Sctpoint 0.4E6 lb/hr equivalent stcam Hotc: flow setpoint is below nominal flow at 755 psig and Tavg << full power flow and therefore this 545 F port'ion of logic is made up at power Accident analysis sctpoint N/A Not explicitly modeled Delay time H/A Not explicitly modeled. Steam line isolation is assuaed concurrent with SI (i.e. 2 s delay + 5 s valve stroke) 10.2.4.3 High-high stcam flow, coincident SI Nominal Setpoint 3.6E6 lb/hr equivalent stcam flow at 755 psig Accident analysis setpoint N/A ~ Hot explicitly modeled Delay time H/A Hot explicitly modeled. Steam line isolation is assuaged concurrent with SI'(i.e. 2 s delay + 5 s valve stroke)

(

10.2.5 Feedwater isolation COLR 24 Cycle 25, Revision 0

Table 1: UFSAR 0Chapter 15 Analysis Setpoints and Xnput Parameters

( Item 4 Xtem/Name Value Remarks:

10.2.5.1 High stem generator water Level Nominal Sctpoint 67X of thc narrow range Instrunent span each SG Accident analysis setpoint 100X of thc narrow range instruaent span each SG Delay time 2.0 Instrunent Loop only 11 0 Original Steam Generators OSG secondary outlet prcssure at OX full power, 1005 ASD setpoint to control Tavg at 547 psig F~

Steam teayeraturc at OX full power, F 547 Assumed m to Tavg OSG collapsed liquid lcvcL at OX fuLL power, X 39 Hominal value, analysis east Justify HRS asswed error band OSG total Liquid mass per SG at OX full power, 130,120 CIRC run using ncw SG conditions with ibm water lcvcl at 55.5X NRL tubcshect)

(38.75'bove OSG secondary outlet pressure at 100X full 815 This value is for OX plugging and a power, psig fouling factor of .00002.

Steam temperature at 100X full power, F 522.5 This value is for ncw SG conditions OSG collapsed liquid level above tube sheet at 38.75 This is a maximus value, used to 100X full power, ft generate this mass value below. A minimua value would be 35.5 XNRL.

OSG total liquid mass pcr SG at 100X full power, 85,410 Value considered steam generator new Lbm conditions, with water Level at 55.5X I

narrow range (38.75'bove tubeshect)

Heat load per SG, Btu/hr 2602000000 Primary flow pcr SG, Lb/hr - Design 33600000 Stcam flow per SG, Lb/hr - Design 3290000 Secondary design pressure, psig 1085 Secondary design temperature, F 556 No. of tubes per SG 3260 Tube DO, in. 0.875 Tube avcragc wall thickness, in. 0.05 Hinimua wall thickness not specified",

Haximua moisture carryover, X 0.25 Secondary heat transfer area, ft~ per SG 44,430 Primary heat transfer area, fthm per SG 39,406 Tube length(s)

Haximua, ft 71 ~ 365 Includes tube sheet (2*22)

Hinimm, ft 57.146 Includes tube sheet (2*22)

Average effective length, ft 59.5 Above tube sheet Overall OSG bundle height, ft elevation - 286.549 ft or Tube shcct thickness is 22 inches 33.031 ft above bottom of tube sheet Harrow range level tap locations (clcvations), 287.474/299.401 ft Wide range level tap locations (elevations), ft 256.349/299.401 Secondary nozzle to nozzle dP Q full power, psi 16.5 Estimate value COLR Cycle 25, Revision 0

{

Table 1 UFSAR C apter 15 Analysis Setpoints and Xnput Parameters Item g Xtem/Name Value Remarks:

Primary nozzle to nozzle dP with no plugged 32.3 psi 9 flow ~ 33.64E6 tubes lb/hr Secondary volune, ft (water volune Q 1525/0 1681/2821 Kwt) - nominal Secondary volune, ft (steam volune Q 1525/0 2898/1758 Kwt) - nominal Primary total volunc per SG, ft'ot 942.3 leg head volune per SG, 133.4 ft ft'old leg head volune per SG, 133.4 Tube primary volunc per SG, ft 675 ~ 5 Downcomcr level versus downcomer volwe profile Sce NSSL Circulation ratio (100X power) 4,4 An Al'HOS model of the OSG's was used.

Thc Circulation ratio is the downcomcr fLow divided by the outlet flow. Confirmed with CLRC run.

Total volune versus level Sec NSCL SG Primary Head Cladding Thickness 5/16 Kaxinzln SG tube leakage, gpm 0.5/SG ActuaL value limited to 0.1 gpn/SG due to stress concerns COLR 26 Cycle 25, Revision 0

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