ML17264A678

Rev 1 to Colr.

ML17264A678
Person / Time
Site:	Ginna
Issue date:	05/24/1996
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
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ML17264A623	List: ML17264A622 ML17264A678 ML17264A679
References
NUDOCS 9610090392
Download: ML17264A678 (40)

Text

COLR GINNA STATION Cycle 26 Revision 1 CORE OPERATING LIMITS REPORT (COL R)

Re ponsible anager Effective Date Controlled Copy No.

'P6i00'903'yl2 961004 PDR ADOCK 05000244 P PDR

7 )

R.E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 26 Revision 1 This report is not part of the Technical Specifications. This report is referenced in the Technical Specifications.

S )

"l

TABLE OF CONTENTS 1.0 CORE OPERATING LIMITS REPORT ................... 2 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 . ~ ~ ~ ~ ~

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 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ 6 FIGURE 1 - RE(UIRED SHUTDOWN MARGIN . 7 FIGURE 2 - CONTROL BANK INSERTION LIMITS 8 F IGURE 3 K (Z) NORMALIZED Fo (Z) AS A FUNCTION OF CORE HE IGHT 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 COLR Cycle 26, Revision .1

R.E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 26 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 26, Revision 1

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,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 MODFS 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 above 70% RTP.

The EOL ARO/RTP - MTC shall be less negative than -42.9 pcm/ F.

where: ARO stands for, All Rods Out

'OL 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.

'COL R Cycle 26, Revision 1

I

,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) ~ gF g"K(Z) when P > 0.5 P

F,(Z) ~ Z,y.K(Z) when P z 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" g (LCO 3.2.2)

(Limits generated using Reference 1) 2.6.1 F"~ ~ 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 provided by Procedure RE-11. 1.

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

COLR 'Cycle 26, Revision 1

, 2.8 RCS Pressure Tem erature and Flow Oe arture from Nucleate Boilin (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 s 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 ~ 2300 ppm.

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 (AFM) 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 26, Revision 1

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4.0 REFERENCES

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

2. WCAP-10054-P-A and WCAP-10081-NP-A, "Westinghouse Small Break ECCS Evaluation Model 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 Hethodology, Volume 2: Application to Two-Loop PWRs Equipped with Upper Plenum Injection," December 1988.

WCAP-10924-P-A, Rev. 2 and WCAP-12071, "Westinghouse Large-Break LOCA Best Estimate Methodology, Volume 2: Application to Two-Loop PWRs Equipped With Upper Plenum Injection, Addendum 1: Responses to NRC guestions," December 1988.

WCAP-10924-P, Volume 1, Rev. 1, Addendum 4, "Westinghouse LBLOCA Best Estimate Methodology; Model Description and Validation; Model Revisions," August 1990. [Approved by NRC SER dated 2/8/91]

WCAP-8395, "Power Distribution Control and Load Following Procedures -

Report," September 1974. 'opical

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

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

COLR Cycle 26, 'Revision 1

3 8 ONE LOOP (0, 2AS)

OPERAllON o>

0 ACCEPTABLE Cl OPERATION 2

0'U (0,1 80)

TWO LOOP (1500, 1A5) OPERAllON (9

$ 1

($ 500, 1.00)

UNACCEPTABLE OPERATION

(

1500 1000 500 COOLANT BORON CONCENTRATION (ppm)

FIGURE I REQUIRED SHUTDOWN MARGIN COLR Cycle 26, Revision I

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220 1034,') 66.6,'

200 B Bank (100, 104)

~~ '180 (0, 104 5 <6O CB ank

~140

&120 DBank

~

o 100 o 80 60 (0,53) co 40 (O o 20 (30.

0 0 10 20 30 40 50 60 70 80 90 100 Core Power (Percent of 1520 MWT)

• The fully withdrawn position is defined as > 221 steps.

( FIGURE 2 CONTROL BANK INSERTION LIMITS COLR Cycle 26, Revision 1

N

+ 1.0 0

O Gf 008 U)

CL I 06 (5

Total F = 2.450

~ ~

6$

~Elt 0.0

~K 1.0 0.4

'11.783 1.0 6

N

~ ~

6$

E02 0

0.0 0.0 2.0 4.0 6.0 8.0 10.0 11.783 Elevation (ft)

FIGURE 3 K(Z) - NORMALIZEO Fo(Z) AS A FUNCTION OF CORE HE IGHT COLR Cycle 26, Revision I

l00 00 NOT OPERATE IN THIS AREA WiTH AFO OUTS(OE THE TARGET BANO

(-11,90) 80) 80 ACCEPTABLE

~A OPERATION 0 VIITHAFD

"" """ """ OUTSGE THE"""

TARGET BAND MATH <1 HR PENALTY Q 60 DHRAT(ON TIME zlY (<1,60) (31/0)

I- 40 Cl ACCEPTABLE l~ OP ERAT)ON 20

-30 -20 -50 0 10 20 30 AXlALFLUX DlFFERENGE (/0)

FIGURE 4 AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS ANO TARGET BANO LINITS AS A FUNCTION OF RATEO THERMAL POWER COLR 10 Cycle 26, Revision I

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

1.0 Reactor Cootant System (RCS)

Upper head votune, ft 300.0 Above upper support plate.

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

~

of fucL votIÃIQ, ft 50.3 Top of active fuel to bottom of upper ccrc 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 volune.

Active fuel volune, ft 367.6 Bottom of fuel to top of fueL Bottom of fuel volune, ft* 11.0 Top of loucr core plate to bottom of active fuel.

Lower Plenun votune, ft fthm 514.3 Below top of lower core plate Oouncaner volune, above bottom of cold Leg, ft 138.4 Above bottom of cold lcg elevation to bottom of upper support plate Douncomer, Louer ccrc plate to elevation of the 278.2 Top of Lower core plate to elevation bottom of the cotd leg volune, ft of bottom of cold lcg Barrel baffle, lower core plate to upper core 128.5 Top of lower core plate to bottom of plate volune, ft upper core plate.

Total volunc, ft 2449.1 Includes nozzles Hot teg pipe volune per loop volune, 78.7 Cold leg volunc per loop + cross over, ftn cross over = 140.7 cold leg ~ 46.8 RC punp volune pcr purp, ft 192 Cold leg pipe ID, in. /Pump suction IO, in. 27.5/31 Hot leg 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 Sec NS&L Homologous Curves arc available in coolant punps/Hanologous Curves RETRAH Rated RC pump head and flow, ft & gpm 252; 90,000 Rated RC pump torque and efficiency 9 rated 84X efficiency at hot head/flow, ft-lb, fraction conditions RCP Pump Rated Pouer (hot, 556 degrees F) 4842 BHP RCP Kotor Rated Speed, RPH 1189 Hcment of inertia of pump and motor, lb-ft 80,000 RC pump heat, Hut (max/min pcr pump) 5, 4 Pump pouer var>es w>th RCS tenp fran approx 4 Hut to 5 H'Mt 1.2 Core Rated power, Hut 1520 COLR Cycle 26, Revision 1

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

Reactor power uncertainty, X RTP Bypass, X 6.5 Thimble plugs removed.

Upper head bypass, X Il proprietary Upper head temperature, degrees F 590 High T~ value.

Heat transfer area, ft 26,669 Average core heat flux, Btu/hr-ft 189,440 1.3 Fuel Asscmbl ics 1 3.1 Height TotaL, inches (length from bottom of assembly 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 Hass of clad, Lbm 25,927 HINbcr of fuel pins per fuel assembly (FA) 179 Ho. of Fuel Assemblies 121 Fuel pin pitch, in. 0.556 gotten nozzle weight and volune 9.1 lbs.

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

62.9 in*

Fuel Assembly resistance (core dP f(flow)), psi core delta P ~ 20 psi

"-170,200 Thimble plugs removed.

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

1.3.3 Fuel pin geometry Pellet diameter, in. 0.3444 Clad 00/LD, in./in. 0.400/0.3514 1.3.4 Control Rod 4 lnstrisncnt Guide Tubes Ho. of control rod guide tubes 16 Ho. of instrwent guide tubes Control Rod Guide tube upper part 00/LD, in. /in. 0.49/0.528 instrunent Guide tube 00/LD, in. /in. 0.395/0.350 Guide tube lower part OO/LD, in./in. 0.4445/0.4825 Control Rod Drop Times, maxinuns, sec. Hon-LOCA 2.4 Allowances are added to thc Tech Spec LOCA 3.0 aLLowable value.

Control rod maximun withdrawal rate, in./min. 45 Control rod maximun insertion rate, pcm/sec. 90 i Control rod insertion limits Hot channel radial peaking factor See COLR 1.75 COLR 12 Cycle 26, Revision 1

Table 3.: UPSAR Chapter 15"Analysis Setpoints and Input Parameters Item/Name Value Remarks:

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 secure[ation Code safety valve open time 0.8 sec seal clearing time Crosby Kodel HB-BP-86, size 4K26 Code safety valve sctpoint 2485 psig Tolerance is + 2.4X/-3X.

Spray valve number 2 Spray valve f lou capacity, gpm/valve 200 Spray valve setpoint- start open/full open 2260/2310 Proportional Spray valve time constant, sec. 5 Assumed value PORV nwber 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 E11GK-HSAE1, with a time response of 1 scc (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 sctpoint [normal] open/close, psig 2335/2315 PORV sctpoint [LTOPJ open/close, psig 430 PORV bloudoun characteristic Keater capacity w/ bank capacity and setpoints, 800 kM Control banks 0 kM at 2250 psig and 400 kM at 2220 psig Backup Keatcrs Full on at 2210 psig and resets at 2220 psig Hiniaun heater capacity required for LOOP, kM 100 Heater bank controller type proportional 400 kM 1.4.1 Pressurizer vol ae(s) (100X / OX power)

Mater, ft (100X / OX power) 396/199 Steam, ft~ (100X / OX pouer) 404/601 Total, fta 800 Pressurizer [D, ft-in 83.624 in / cladding thickness is 0.188 in Surge line [0, in. 8.75 Surge line is 10 in schedule 140 Spray line ID, in. 3.062 Surge line volune, ft 18.4

(

COLR 13 Cycle 26, -Revision 1

l I Table 1- UPS'AR Chapter 15 Analysis Setpoints and Xnput Parameters Xtem/Name Value Remarks:

1.4.2 Pressurizer Level Lower level tap elevation 257' Upper level tap elevation Pressurizer tevcl is linearly 275'power Pressurizer level vs X power Level ramped 0 X 35X bctwcen these points. Hot used in 100 X 50X Chapter 15 analyses.

Distance Hot Leg Centerline to Lower Tap, ft 10.750 Haxianan level allowed for steam bubble, X 87 1.5 RCS Flows, Tcmpcratwe and Pressures Total reactor coolant flow, gpm (15X plugging) 170,200 Use for non DHS Total reactor coolant flow, gpm (15X plugging) 177,300 Usc for statistical DHB Average reactor cootant temperature, degrees F 559 to 573 '/547 Cycle 26 T~ ~ 561 (Full power/HZP)

Reactor cootant pressure, psig 2235 Reactor coolant flow uncertainty, X nominal 4 Reactor coolant temperature umertainty, degrccs 4 F

Reactor coolant pressure uncertainty, psi s 30 DHB Limit (safety analysis limit) 1 '0 (s 1.6 'ow Tcaperaturc Ovcrprcssurc Protection (LTOP)

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

Haxiaun pressurizer level for RCP start, X 38 1.7 Fuel Handling/Dose Calculations Haxianan reactor coolant gross specific activity 100/E pCi/gm Haxiaaan reactor coolant dose cquivalcnt i-131 1.0 pCi/gm Haxianjn secondary coolant dose equivalent i-131 0.1 pCi/gm Hinianan reactor coolant boron concentration, ppm 2000 Hinianan reactor coolant level 23 ft above flange Hiniaxan spent fuel pool level 23 ft above fuel Hinianan spent fuel pooL boron concentration, ppm 300 Hinianan spent fuel pool charcoal filter 70 TS testing requires 90X eff.

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

efficiency, X methyl iodine renoval Hinimun control room charcoat filter efficiency, 70 TS testing requires 90X eff.

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

' Source Terms used for dose calculations ORGEH 2 Dose conversion factors ICRP-30 COLR Cycle 26, Revision 1

l f

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

Haxinun Gas Decay Tank Xenon-133 concentration, 100,000 Ci 2.0 Nain Feeduater (HFM)

Feeduatcr tenperaturc versus load Power Tenperature 100X design tenp is 432 degrees F 102X 425 F 70X 385 F 30X 322 F OX 100 F Fceduatcr Suction Tenperature vs Power, nominal Power Tenperature P 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 NPSH curves Head-Capacity and NPSH curves for main fceduater Sce NS&L Sclectcd flow splits arc provided for ixslps model validation.

Nain Fecduatcr pmp - Rated Head Hain Feeduater pump - Rated Torque Hain Feedwater punp - Homent of inertia 2150'89.612 Elevation of steam generator inlet nozzle Elevation of main fcedwatcr pump, ft 257.75 Elevation is at center of shaft Elevation of condensate lxmp, ft 250.833 HFW regulating valve open time on demand, scc NFW regulating valve close time on demand, scc 10 HFW regulating valve Cv, full stroke Assumed value. Actual value "

-684.

Low load HFM regulating valve Cv, (bypass 48.7 Effective Cv: includes bypass linc valves)

HFM Heater resistance .(delta P) sec NS&L Design data on the High Pressure Heaters (2 in parallel) is provided 3.0 Auxiliary Fcedwatcr CARI)

Hinimzn design tcnperature of the water source 32(*), 50 initial AFW water source arc the CSTs service water / CST (degrees F) located in the Service Bldg. Safety Related source is thc Service Mater system (lake) ~

• Value different for CNHT integrity.

Haximm design tenperature of the water source 80, 100 initial AFW water source are the CSTs service water / CS1'degrees F) located in the Service Bldg. Safety Related source is the Service Water system (lake) ~

Startup time for the auxiliary fcedwatcr pwps, *TDAFM starts on LO level (17X) in scc both gens or UV on both unit 4Kv busses. HDAFW starts on Si (seq), or LO level either SG, or trip of both HFP or AHSAC Hinimsn delay for AFM start, scc TDAFM - 0, HDAFW - 1 HDAFM acceleration time test results show approximately 1.5 s.

COLR 15 Cycle 26, .Revision 1

Table 3.: UFSAR Chapter 15 Analysis Setpoints and Xnput Parameters Xtem/Name Value Remarks:

Haximwa delay for AFII start, sec HDAFII - 47, TDAFII at For HOAFII, LOOP on sequencer is 47 LO Level both SGs sec. TDAFII starts at nominal 17X in both SGs AFII control valve open time on demand, sec H/A HDAFII control valves are normally open and throttle closed to controL flow between 200.230 gpm AFII control valve Cv(flow is f(dP)l HOAFIIP valves arc 3 Rockwell model II A4006JKHY stop check valves. TDAFII controL valves (4297, 4298) are 3 Fisher g470-HS.

TOAFMP, maximus flow, gpm 600 AFII, minim!a flows, both generators intact, gpm TDAFIIP 200/SG SBLDCA assIInes 200 gpm per SG with HOAFIIP 200/SG thc failure of one DG Hinimun delay for standby AFII start, min 10 4.0 Hain Stets'ystem (HS)

Location (and elevation) of condenser dump CSD - elev 256'.875 valves and atmospheric relief valves ARV - elev 289'.563 Full load stcam line prcssure drop, psi approx 45 This estimate, to thc governor valves, is provided for comparison purposes only.

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

HS Isolation valve Cv [flow is f(dP)) HSIV - 23500 check valve - 17580 Hain Stern Code Safety Valves Number of vaLves (4 pcr linc) 8 Valve flow capacities - Total, ibm/hr 6621000 Rated flow (3X accunulation pcr ASHY,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 Humber of valves in bank Valve setpoint(s), (first/last three), nominal, 1085/1140 are Crosby PHA-65 6R10 Setpoint tolerance is +1X / -3X.

ps I g 1m'alves Hodel valve setpoint at 1.01 (nominal), and full flow at 1.04

( Valve blowdown characteristic 15X max (nominal).

COLR 16 Cycle 26, Revision 1

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

4.2 Atmospheric relief valves Ho. Atmospheric relief valves 2 Atnospheric relief valve sctpoint/Air-operated, 1050 During Hot Standby operation setpoint psig is lowered to control no load Tavg Atmospheric relief valve setpoint/gooster, psig 1060 Atmospheric relief valve capacity, ibm/hr 313550 at 1060 psig Max flow is 380000 5.0 Turbine Generator (TG) 5.1 Corxienscr Ho. of condenser dwp valves Condenser dwT> valve open time, sec Condenser dump valve close time, sec Assuning close time = opening time Condenser dump 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, sctpoints as described. On 10X step Tref+20 4 valves load decrease same ratio with a 6F dcadband from Tref Condenser dump valve Cv (flow is f(dP)] Design Cv (240) from design conditions (302,500 ibm/hr sat stcam at 695 psig) 6.0 Chemical and Vol~ Control System (CVCS) c CVCS capacity/pump 3 pwps, 60 gpn max each Normal ops: 2 charging pwps - one is manual at 15-20 gpn and the other in automatic. Charging pumps are POPs w/ 46 gpm total - 8 gpm to seals - 3 gpm leakage + 5 gpm into RGB 40 gpm letdown CVCS minimum/pump, gpm 15 Type of controller (c.g., P + i) and gains PID 100X,180 sec,10 sec 6.1 Reactor Makeup Mater System (RMM)

RMM capaci ty/punp 2 pumps, 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 Minimm RKR Delivery, train failure RCS Prcssure Delivery LOCA Appendix K case. Train failure (psia) (gpm) results in one pwp running with 10X 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 COLR 17 Cycle 26, Revision 1

Table l UFSAR Chapter l5 Analysis Setpoints and Xnput Parameters Xt m/Name Value Remarks:

Hinimm RHR Delivery, two pumps running, one RCS Pressure Delivery LOCA Appendix K case (offsitc power line blocked (psia) (gpm) available). Two pumps running with 155 0 10K degradation with one linc 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 (SI) Delivery vs RCS Prcssure Hinimun SI delivery, 2 ixmps operating, one line Press Delivery Spill LOCA Appendix K case. Train failure spilling (psig) (gpm) (gpm) results in two ixmps running with 5X 1375 0.0 465 degradation with one line'"spilling to 1300 62 465 contairment.

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 Hinimua SI delivery, 3 pumps operating, non-LOCA Press Delivery (gpm) Used for non-LOCA transients, 5X pulp (psi a) Loop 'A Loop degradation l8 I 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 COLR 18 Cycle 26, Revision 1

'El Table 1: UFSAR Chapter 15 Analysis Setpoints and input Parameters

'¹ Xtem/Name Value Remarks:

Hinisxma Si delivery, 2 pcs operating non-LOCA Press Delivery (gpm)

'A'oop Used for non-LOCA transients, 5X lxmp (psia) Loop degradation.

IBI 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 Haximua Si delivery, 3 pumps operating, SGTR Press Loop A Loop B The KYPIPE model assunes no pump (psig) (gpm) (gpm) degradation. Loop A and B'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 Acauulators Number of accunulators 2 Total volune, each, ft 1750 Liquid voluae, ft - min/max 1126/1154 Liquid volune, ft - Best Estimate 1140 initial pressure, psig - Kinimun / Haxisun 700/790 initial temperature, F 105 LBLOCA Boron concentration, ppm (min/max) 2100/2600 Note - EO analyses use a maxisxIa concentration of 3000 ppm 7.4 RMST RUST Temperature, min / max, degrees F 60 / 80 Hinimua RIIST volwe, gal 300,000 RUST boron concentration, ppm (min/max) 2300/2600 Note - EQ analyses usc a maximm concentration of 3000 ppm 8.0 Contairaent Initial containment pressure, psia min - 14.5 Hinimua is used for LOCA analysis.

max - 16.7 Haximua is used for the contairaent integrity cases (SLB).

COLR 19 Cycle 26, Revision 1

Table 1: UFSAR Chapter 15 Analysis Setpoints and Xnput Parameters

¹ Xtem/Name Value Remarks:

Initial containment teaperature (LOCA/SLB) 90/120 LOCA teaperaturc lower for PCT degrees F calculations. SLB higher for containment integrity Initial relative hunidity, X 20 SM temperature min/max, degrees F 35/80 Haximun containment leakage, wtX/day 0.2 8.1 Contairwent Heat Sinks Listing of Passive Heat Sinks, quantities, see HSTL materials, and configurations 8.2 Densitics, Thermal Conductivitics and Heat Capacities of Heat Sinks Insulation density, conductivitycapacity 3.7 ibm/ft'.0208 BTU/hr F ft 1.11 BTU/ft~ F 150 ibm/ft note: minimsa conductivity 0.81 BTU/hrFft corresponds to maximm density, and 31.5 BTU/ft F mexican conductivity corresponds to miniaua density.

Steel density, conductivity, capacity 490 Ibm/ft'8 BTU/hrFft 54.4 BTU/ft F Stainless steel density, conductivity, capacity 496 Ibm/f t'5 BTU/hrFft 54.6 BTU/ft F (Qs Containment free volune, min / max, cu. ft. 1,000,000 / 1,066,000 Ground Teeperaturc (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 Contairment fan cooler performance Tarp Hin Hax (deg 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 Contairmcnt spray flow , min / max, each, gpm 1300 / 1800 8.3 Delays for CRFCs and Spray Pimps CRFC delay, offsitc power available, seconds 34 includes 2.0 sec SI delay CRFC delay, offsitc power not available, seconds includes 2.0 sec SI delay Containment Spray, 1300 gpm each pump, maxima 28.5 - one purp This delay is from the time delay, sec 26.8 - two purps Contairwent Hi-Hi sctpoint is reached. It includes instrunent delay and spray linc fill time.

Contairrncnt Spray, 1800 gpm each pmp, mininun 9 / (14 w LOOP) This delay is from thc time of brcak.

delay, scc Contairmcnt Design pressure, psig 60 Distance Basement floor to Springline, feet 95 Distance Springline to top of dome, feet 52.5 COLR 20 Cycle 26, Revision 1

l g

Table 1,: UPSAR Chapter 15 Analysis Setpoints and Input Parameters Item/Name Value Remarks:

8.4 Conte irment Suep Ninimua wtX of HaOH Tank 30 9 0 Control Systems (Reactor, FM, Przr level ~ Turbine, AFM)

Tavg versus power H/A Tavg ranps linearly from 547 degrees F at OX power to 561 degrees F at 100X power Pressurizer pressure and level algorithms H/A Pressurizer pressure sctpoint 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 Protection System 10.1.1 Power range high neutron flux, high setting nominal 1.09 accident analysis 1.18 delay time, sec 0.5

/

0.1.2 Power range high neutron flux, low setting nominal 0.250 accident analysis 0.350 delay time, sec 0.5 10.1.3 Overtcmperature delta T nominal Variable accident analysis Variable delay time, sec 6.0 Total delay time - fram the time the tecperature 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 Hot explicitly modelled in safety analysis delay time, sec 2.0 10.1.5'igh pressurizer pressure nominal, psig 2377 accident analysis, psia 2410 delay time, sec 2.0 0.1.6 Low pressurizer prcssure COLR 21 Cycle 26, Revision 1

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

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 91X of normal indicated flow accident analysis 87X per loop delay time, scc 1.0 10.1.8 Low-low SQ level nominal 17X of thc narrow range Hhile trip sctpoint could bc as low 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 (low fluid oil pressure) nominal, psig 45 accident analysis H/A Hot explicitly modeled in safety analysis delay time, scc 2.0 10.1.10 Unde rvoltoge nominal, V 3150 accident analysis Safety analysis asswes RCCAs arc released 1 ' scc. after setpoint is rel cased.

delay time. sec 1.5 10.1.11 Under frequency nominal, Hz 57.7 accident analysis 57.0 Analysis is performed but not explicitly modeled in safety analysis.

delay time 1.2 Safety analysis assuncs RCCAs are released 1.2 sec after setpoint is reached.

10.1.12 intermediate range nominal, RTP 0.25 Hay fluctuate due to core flux safety analysis, RTP N/A Hot explicitly modclcd in safety analysis delay time, sec 0 ~ 1.13 Source Range COLR 22 Cycle 26, Revision j.

Table 1.: UPSAR Chapter 15 Analysis Setpoints and Xnput parameters Xtem/Name Value Remarks:

nominal, cps 1.4E+5 Highest nominal value accident analysis, cps 1.DE+5 delay time, sec 2.0 10.1 14 Hfgh 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 Injection System 10.2.1.1 High contafrmcnt prcssure Noninal setpoint, psig 4.0 Accident Analysis setpoint, psig *only modeled in accident analysis for start of contafwent fan coolers.

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

10.2.1.2 Low pressurizer prcssure Nominal setpoint, psig 1750

( Accident Analysis sctpoint, psia Delay time, sec 1785, SGTR 1730, non-LOCA 1715, LOCA 2.0 10.2.1.3 Low stcam linc prcssure Hominal setpoint, psig 514 Accident Analysis setpoint, psig 372.7 Sce NSIL Delay time~ sec 2.0 Sec HSCL 10.2.2 Contalreent Spray Hominal Setpoint, psig 28 Accident analysis sctpoint, psig 32.5 Sec NS8L Delay time, sec 28.5 Delay time includes time to fill lines. See NS&L 10.2.3 AFM System Low-low steam generator water level Nominal Setpoint 17 X of narrow range instrunent span each stcam 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 containment tecperaturc of 286 F Delay time, sec 2.0 COLR 23 Cycle 26, Revision 1

I I Table 11 UFSAR Chapter lS Analysis Setpoints and Input Parameters Item/Name Value Remarks:

10.2.4 Steam Line Isolation 10.2 4.1 High contairwent pressure Nominal Setpoint, psig 18 Accident anaLysis setpofnt H/A Not explic>tly modeled Delay time H/A Not explicitly modeled 10.2.4.2 High steam flow, coincident with low Tavg and SI Nominal Setpoint 0.466 Lb/hr equivalent steam Note: flow setpoint is below nominal flow at 755 ps'ig and Tavg < full power flow and therefore this 545 F portion of logic is made up at power Accident analysis setpoint H/A Hot explicitly modeled Delay time H/A Not explicitly modeled. Stcam line isolation is assigned concurrent with SI (i.e. 2 s delay + 5 s valve stroke) 10.2.4.3 High-high steam fLow, coincident'I Hominal Setpoint 3.6E6 lb/hr equivalent stcam flow at 755 psig Accident analysis sctpoint H/A Hot explicitly modeled Delay time H/A Hot explicitly modeled. Steam Linc 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 steam generator water level NominaL Sctpoint 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 Instrunent loop only 11.0 8WI Ste~ 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 pcr 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 Haximsn moisture carryover, X 0.10 Narrow range lcvcl tap locations, inches above 386 /a / 529 /e TS secondary face Wide range level tap Locations, inches above secondary face TS 8 /~ / 529 /e 1.1 SG Pressure Drops COLR Cycle 26, Revision 1

f I e

Table 3,: UFSAR Chapter 15 Analysis Setpoints and Input Parameters Item/Name Value Remarks:

Secondary nozzle to nozzle dP Q fuLL power, 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 unrecovcrable pressure PluggingX ap psi See associated flows for X plugging.

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

Hinirlmr tube length, ft 55.925 includes length in tubeshect (2x25.625")

Average length, ft 61.988 includes length in tubesheet (2x25.625")

Hinimun U-bend radius, inches 3.979 Note: this is not the bend radius for the shortest tube.

Kaximun 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 face, inches (min/max/average) 303 /rn / 310 /i / 308.182 Secondary heat transfer area, ft* per SG 54,001 Primary heat transfer area, fthm per SG 47,809 Overall bundle height, ft above secondary face 30.427 of TS Tube material SB-163 Alloy H06690 SG Tube Haterial Thermal Conductivity, Tarp F Conductivity BTU.in/hr-ftz-F 200 93

,300 100 400 107 500 114.5 600 122 SG Tube Haterial Specific Heat, BTU/lb-F Tarp 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 HRL, ft 5.703 11.3 SG Voluncs 11.3.1 SG Secondary Side Volunes Secondary volunc, ft (total) 4512.7 Secondary volune up to lower NRL tap, ft 1893.2

( Secondary volunc up to upper HRL tap, ft 3460.4 COLR 25 Cycle 26, Revision 1

(

Table 2,= UPSAR Chapter 15 Analysis Setpoints and Xnput Parameters Xtem/Name Value Remarks:

11.3.2 Riser Voluacs Secondary side bundle voiune (TS to top of U- 1281.8 bend inside shroud), ft*

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

over point, fta 11.3.3 Dmncomcr Vol~

Downcomer volune, top of TS to top of U-bend, 359.6 ft Downcomer voluae, top of U-bend to spill-over 1437.3 point, fthm 11.3.4 SG Primary Side Voluaes Inlet plena per SG, ft* 129.65 Outlet pienun per SG, ft 129.65 Tube primary voluae per SG, 710.3 total voluac pcr SG, ft ft'rimary 969.6 Circulation ratio (100X power, clean, unplugged) 5.39 Circulation ratio = bundle flow /

steam flow. Assunes 40,000 Ibm/hr b lowdown.

Tubesheet thickness, inches 25.625 Includes cladding.

11 4 SG Primary Side Dimensions Primary head radius, inches 58.375 Radius to clad surf acc.

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 pienua, inches Nozzle lengths, inches cylindrical section 8.75 conical,section 13.0 total length 21.75 Neigth from SG primary head bottom (outside) to 9o'/io top of TS, inches Distance tube shcct primary face to hot leg 6.654 centerline, ft 11.5 SG Secondary Side Dimensions Lower shell inside diamctcr, inches 122 Lower shell thickness, inches 2.875 Tube shroud inside diamctcr, inches 114 Distance top of tube bundle to top of steam 298.5 nozzle, inches Steam nozzle flow rcstricter area, ftz 1.4

( Distance secondary face of TS to ccntcrline of fecdwater nozzle, inches 407 /I COLR 26 Cycle 26, Revision 1

I Table 1: VPSW Chapter l5 Analysis Setpoints and Xnput Parameters em g Xtem/Name Value Remarks:

(

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 spilt-over point, 178.0 This value is equivalent to thc riser inches height for the OSG.

Primary side roughness, micro-inches Hozzles, head 60 Values given are conservative Tubes 60 assumptions.

11.6 SG Secondary Side Mater Hasscs Secondary water inventory, 100X power, T 86,259 liquid Best estimate vaLue 573.5, no plugging, ibm 5,286 steam Secondary water inventory, 100X power, T,~ = 85,547 liquid Best estimate value.

559, no plugging, Lbm 4,675 steam 11.7 SG Primary Side Head Loss Cocfficicnts SG inlet nozzle/plenums loss coefficient, ft/gpm~ 1.01E-09 for ID = 31.2" SG outlet nozzle/plerwn loss coefficient, 3.31E-10 for ID = 31.2" ft/gpm SG tubing loss coefficient, ft/gpm~ 9.62E-09 for OX plugging For tube ID ~ 0.664'<, A = 11.458 1.32E-08 for 15X plugging ft', A,~~ 9.739 ft~. Plugging is assumed to be uniform.

SG tubing loss coefficient, straight section 4.19E-09 for OX plugging 'For tube ID = 0.664", A ~ 11.458 (in), ft/gpm~ 5.73E-09 for 1SX plugging ft~, A<<c 9.739 ft~. Plugging is assumed to be uniform.

SG tubing loss coefficient, U-bend section, 1.02E-09 for OX plugging For tube ID -"0.664<<, Ao= 11.458 1.40E-09 for '15X plugging ft', A,~>> = 9.739 ft'. Plugging is assumed to be uniform.

SG 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 ft, A,s= 9.739 ft . Plugging is assumed to be uniform.

27 Cycle 26, Revision 1