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

GINNA STATION COLR Cycle 26 Revision 1

CORE OPERATING LIMITS REPORT (COLR)

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

2. 1 SHUTDOWN MARGIN.

2.2 MODERATOR TEMPERATURE COEFFICIENT 2.3 Shutdown Bank Insertion Limit.

2.4 Control Bank Insertion Limits 2.5 Heat Flux Hot Channel Factor (Fo(Z))

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

2.7 AXIAL FLUX DIFFERENCE 2.8 RCS Pressure, Temperature, and Flow Departure from Boiling (DNB) Limits 2.9 Boron Concentration

~

~

~

~

~

Nucleate 3

3 3

3 4 '

4 5

5 3.0 UFSAR CHAPTER 15 ANALYSIS SETPOINTS AND INPUT PARAMETERS.....

5" 4 ~ 0 REFERENCES

~

~

~

~

~

~

~

~

~

~

~

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~

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~

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FIGURE 1 - RE(UIRED SHUTDOWN MARGIN.

FIGURE 2 -

CONTROL BANK INSERTION LIMITS F IGURE 3 K(Z)

NORMALIZED Fo (Z) AS A FUNCTION OF CORE HE IGHT o

~

~

~

FIGURE 4 - AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AND TARGET BAND LIMITS AS A FUNCTION OF RATED THERMAL POWER 6

7 8

9 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 3.1.3 3.1.5 3.1.6 3.2.1 3.2.2 3.2.3 3.4.1 3.9.1 "SHUTDOWN MARGIN (SDM)"

"MODERATOR TEMPERATURE COEFFICIENT (MTC)"

~"Shutdown Bank Insertion Limit" "Control Bank Insertion Limits" "Heat Flux Hot Channel Factor (Fo(Z))"

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

"AXIAL FLUX DIFFERENCE (AFD)"

"RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits" "Boron Concentration" COLR Cycle 26, Revision 1

l I

,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 2.1.2 2.1.3 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.

The SHUTDOWN MARGIN in MODE 4 when both reactor coolant pumps are not OPERABLE and in operation and in MODE 5 shall be greater than or equal to the one loop operation curve of Figure 1.

The SHUTDOWN MARGIN required in LCOs 3.1.4, 3.1.5, 3.1.6,

3. 1.8, and 3.4.5 shall be greater than the limits specified in Figure 1 for the number of reactor coolant pumps in operation.

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.

'COLR Cycle 26, Revision 1

I

,2.4 Control Bank Insertion Limits (LCO 3. 1.6)

(Limits generated using Reference 1) 2.4.1 2.4.2 The control banks shall be limited in physical insertion as shown in Figure 2.

The control banks shall be moved sequentially with a 100

(+5) step overlap between successive banks.

2.5 Heat Flux Hot Channel Factor F

Z (LCO 3.2. 1)

(Limits generated using References 1 and 2) 2.5. 1 Fo(Z) ~ gF g"K(Z) when P > 0.5 P

F,(Z) ~ Z,y.K(Z) 0.5 when P z 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))

where:

F ATP 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 2.7.2 The AXIAL FLUX DIFFERENCE (AFD) target band is + 5%.

The actual target bands are provided by Procedure RE-11. 1.

The AFD acceptable operation limits are provided in Figure 4.

COLR

'Cycle 26, Revision 1

, 2.8 RCS Pressure Tem erature and Flow Oe arture from Nucleate Boilin (Limits generated using Reference 4) 2.8.1 2.8.2 2.8.3 The pressurizer pressure shall be a 2205 psig.

The RCS average temperature shall be s 577.5 'F.

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

1 I I 0

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

'opical Report,"

September 1974.

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

o>0 Cl 2 0'U (9

1

(

(1500, 1A5)

($ 500, 1.00)

ACCEPTABLE OPERATION ONE LOOP OPERAllON TWO LOOP OPERAllON UNACCEPTABLE OPERATION (0,1 80)

(0, 2AS) 1500 1000 500 COOLANT BORON CONCENTRATION (ppm)

FIGURE I REQUIRED SHUTDOWN MARGIN COLR Cycle 26, Revision I

J I

220 200

~~ '180 5 <6O

~140

&120

~o 100 o

80 60 (O

co 40 o

20 0

0 (0, 104 (0,53) 10 1034,')

66.6,'

B Bank (100, 104)

CBank ank DB (30.

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 008 Gf U)

(5I 06 CL 6$

~~

0.4 6N

~~

6$E02 0

Total F = 2.450

~Elt

~K 0.0 1.0

'11.783 1.0 0.0 0.0 2.0 4.0 6.0 8.0 Elevation (ft) 10.0 11.783 FIGURE 3 K(Z) -

NORMALIZEO Fo(Z)

AS A FUNCTION OF CORE HE IGHT COLR Cycle 26, Revision I

l00

(-11,90) 00 NOT OPERATE IN THIS AREAWiTHAFO OUTS(OE THE TARGET BANO 80) 80

~A 0

Q 60 z

lY I-40 Cl l~

(<1,60)

ACCEPTABLE OPERATION VIITHAFD

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

TARGET BAND MATH<1 HR PENALTY DHRAT(ON TIME ACCEPTABLE OP ERAT)ON (31/0) 20

-30

-20

-50 0

10 20 30 AXlALFLUXDlFFERENGE (/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 Upper Plenun volune, ft'op of fucL votIÃIQ, ft Inlet nozzle(s) volune, total of two, ft Outlet nozzle(s) volune, total of two, ft Active fuel volune, ft Bottom of fuel volune, ft*

Lower Plenun votune, ft Oouncaner volune, above bottom of cold Leg, ft Douncomer, Louer ccrc plate to elevation of the bottom of the cotd leg volune, ft Barrel baffle, lower core plate to upper core plate volune, ft Total volunc, ft Hot teg pipe volune per loop volune, fthm Cold leg volunc per loop + cross over, ftn RC punp volune pcr purp, ft Cold leg pipe ID, in./Pump suction IO, in.

Hot leg pipe ID, in.

Design prcssure, psig Design tenperature, F

Cold Lcg and Hot Leg Centerline Elevation 300.0 580.2 50.3 43.2 37.4 367.6 11.0 514.3 138.4 278.2 128.5 2449.1 78.7 cross over = 140.7 cold leg ~ 46.8 192 27.5/31 29 (28.969) 2485 650 246'0" Above upper support plate.

gotten of upper core plate to top of upper support plate.

Includes outlet holes in the barrel

~

Top of active fuel to bottom of upper ccrc plate, inside barrel baffle.

Includes nozzle forging protrusion into vessel.

Does not include mating hole in barrel, this is included in the Upper Plenun volune.

Bottom of fuel to top of fueL Top of loucr core plate to bottom of active fuel.

Below top of lower core plate Above bottom of cold lcg elevation to bottom of upper support plate Top of Lower core plate to elevation of bottom of cold lcg Top of lower core plate to bottom of upper core plate.

Includes nozzles Reactor Coolant Pmp Head-Capacity and HPSH curves for reactor coolant punps/Hanologous Curves Rated RC pump head and flow, ft & gpm Rated RC pump torque and efficiency 9 rated head/flow, ft-lb, fraction RCP Pump Rated Pouer (hot, 556 degrees F)

RCP Kotor Rated

Speed, RPH Hcment of inertia of pump and motor, lb-ft RC pump heat, Hut (max/min pcr pump)

Sec NS&L 252; 90,000 84X efficiency at hot conditions 4842 BHP 1189 80,000 5,

4 Homologous Curves arc available in RETRAH 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

Upper head bypass, X

Upper head temperature, degrees F

Heat transfer area, ft Average core heat flux, Btu/hr-ft 6.5 Il proprietary 590 26,669 189,440 Thimble plugs removed.

High T~ value.

1.3 1 3.1 Fuel Asscmbl ics Height TotaL, inches (length from bottom of assembly to top nozzle)

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

Active, inches 159.935 149.138 141.4 1.3.2 Fuel Assembly Geometry Hass of fuel, ibm Hass of clad, Lbm HINbcr of fuel pins per fuel assembly (FA)

Ho. of Fuel Assemblies Fuel pin pitch, in.

gotten nozzle weight and volune Top nozzle, w/ insert, weight and volune Fuel Assembly resistance (core dP f(flow)), psi f(lb/hr)

Fuel Assembly free flow area, in 105,500 25,927 179 121 0.556 9.1 lbs.

31.5 in 18.15 lbs.

62.9 in*

core delta P ~ 20 psi 9 flow "-170,200 gpn 34.75 Thimble plugs removed.

Single assembly.

1.3.3 Fuel pin geometry Pellet diameter, in.

Clad 00/LD, in./in.

0.3444 0.400/0.3514 1.3.4 i

Control Rod 4 lnstrisncnt Guide Tubes Ho. of control rod guide tubes Ho. of instrwent guide tubes Control Rod Guide tube upper part 00/LD, in./in.

instrunent Guide tube 00/LD, in./in.

Guide tube lower part OO/LD, in./in.

Control Rod Drop Times, maxinuns, sec.

Control rod maximun withdrawal rate, in./min.

Control rod maximun insertion rate, pcm/sec.

Control rod insertion limits Hot channel radial peaking factor 16 0.49/0.528 0.395/0.350 0.4445/0.4825 Hon-LOCA 2.4 LOCA 3.0 45 90 See COLR 1.75 Allowances are added to thc Tech Spec aLLowable value.

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 Code safety valve open time Code safety valve sctpoint Spray valve number Spray valve flou capacity, gpm/valve Spray valve setpoint-start open/full open Spray valve time constant, sec.

PORV nwber PORV flow capacity, ibm/hr PORV Cv PORV open time PORV close time PORV sctpoint

[normal] open/close, psig PORV sctpoint

[LTOPJ open/close, psig PORV bloudoun characteristic Keater capacity w/ bank capacity and setpoints, kM Control banks Backup Keatcrs Hiniaun heater capacity required for LOOP, kM Heater bank controller type 288,000 0.8 sec seal clearing time 2485 psig 2

200 2260/2310 5

2 179,000 50 gpm/(psid)1/2 1.65 sec

+ transmitter 3.95 sec

+ transmitter 2335/2315 430 800 0 kM at 2250 psig and 400 kM at 2220 psig Full on at 2210 psig and resets at 2220 psig 100 proportional 400 kM Rating at 2485 psig plus 3X secure[ation Crosby Kodel HB-BP-86, size 4K26 Tolerance is + 2.4X/-3X.

Proportional Assumed value Steam flow at 2335 psig Rating is for liquid relief. Valve characteristic is quick opening see Copes Vulcan Selecting and Sizing Control Valves 8/75, page 8, Table 18 for Cv vs travel curve.

LTOPs transmitter is Foxboro E11GK-HSAE1, with a time response of 1 scc (time to 90X of final value for step input)

LTOPs transmitter is Foxboro E11GH-HSAE1, with a time response of 1 sec (time to 90X of final value for step input)

(

1.4.1 Pressurizer vol ae(s)

(100X / OX power)

Mater, ft (100X / OX power)

Steam, ft~ (100X / OX pouer)

Total, fta Pressurizer

[D, ft-in Surge line [0, in.

Spray line ID, in.

Surge line volune, ft 396/199 404/601 800 83.624 in / cladding thickness is 0.188 in 8.75 3.062 18.4 Surge line is 10 in schedule 140 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 Upper level tap elevation Pressurizer level vs X power Distance Hot Leg Centerline to Lower Tap, ft Haxianan level allowed for steam bubble, X

257' 275'power Level 0 X 35X 100 X 50X 10.750 87 Pressurizer tevcl is ramped linearly bctwcen these points.

Hot used in Chapter 15 analyses.

1.5 RCS Flows, Tcmpcratwe and Pressures Total reactor coolant flow, gpm (15X plugging)

Total reactor coolant flow, gpm (15X plugging)

Average reactor cootant temperature, degrees F

(Full power/HZP)

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

Reactor coolant pressure uncertainty, psi DHB Limit (safety analysis limit) 170,200 177,300 559 to 573 '/547 2235 4

4 s 30 1'0 Use for non DHS Usc for statistical DHB Cycle 26 T~ ~ 561 1.6 'ow Tcaperaturc Ovcrprcssurc Protection (LTOP)

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

Haxiaun pressurizer level for RCP start, X

1 ~ 1 0/1 38 1.7 Fuel Handling/Dose Calculations Haxianan reactor coolant gross specific activity Haxiaaan reactor coolant dose cquivalcnt i-131 Haxianjn secondary coolant dose equivalent i-131 Hinianan reactor coolant boron concentration, ppm Hinianan reactor coolant level Hiniaxan spent fuel pool level Hinianan spent fuel pooL boron concentration, ppm Hinianan spent fuel pool charcoal filter efficiency, X methyl iodine removal Hiniaun post accident charcoal filter efficiency, X methyl iodine renoval Hinimun control room charcoat filter efficiency, X methyl iodine removal Miniaun time between reactor criticality and fuel movement, hrs.

Source Terms used for dose calculations Dose conversion factors 100/E pCi/gm 1.0 pCi/gm 0.1 pCi/gm 2000 23 ft above flange 23 ft above fuel 300 70 70 70 100 ORGEH 2 ICRP-30 TS testing requires 90X eff.

TS testing requires 90X eff.

TS testing requires 90X eff.

COLR Cycle 26, Revision 1

lf

Table 1:

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

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

Feeduatcr tenperaturc versus load Power Tenperature 102X 425 F

70X 385 F

30X 322 F

OX 100 F

100X design tenp is 432 degrees F

Fceduatcr Suction Tenperature vs Power, nominal P

Feedwater Suction Pressure vs Power, nominal Power 98X 70X 50X 30X Power 98X 70X 50X 30X Tenperature 345 F

319 F

295 F

259 F

Pressure 277 psig 282 psig 305 psig 370 psig 2.1 3.0 Head-Capacity and NPSH curves Head-Capacity and NPSH curves for main fceduater ixslps Nain Fecduatcr pmp - Rated Head Hain Feeduater pump - Rated Torque Hain Feedwater punp - Homent of inertia Elevation of steam generator inlet nozzle Elevation of main fcedwatcr pump, ft Elevation of condensate lxmp, ft HFW regulating valve open time on demand, scc NFW regulating valve close time on demand, scc HFW regulating valve Cv, full stroke Low load HFM regulating valve Cv, (bypass valves)

HFM Heater resistance.(delta P)

Auxiliary Fcedwatcr CARI)

Hinimzn design tcnperature of the water source service water / CST (degrees F)

Haximm design tenperature of the water source service water / CS1'degrees F)

Startup time for the auxiliary fcedwatcr pwps, scc Hinimsn delay for AFM start, scc Sce NS&L 2150'89.612 257.75 250.833 10 48.7 sec NS&L 32(*), 50 80, 100 TDAFM - 0, HDAFW -

1 Sclectcd flow splits arc provided for model validation.

Elevation is at center of shaft Assumed value.

Actual value "-684.

Effective Cv: includes bypass linc Design data on the High Pressure Heaters (2 in parallel) is provided initial AFW water source arc the CSTs located in the Service Bldg. Safety Related source is thc Service Mater system (lake) ~

• Value different for CNHT integrity.

initial AFW water source are the CSTs located in the Service Bldg. Safety Related source is the Service Water system (lake) ~

• TDAFM starts on LO level (17X) in 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 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 AFII control valve open time on demand, sec AFII control valve Cv(flow is f(dP)l TOAFMP, maximus flow, gpm AFII, minim!a flows, both generators

intact, gpm Hinimun delay for standby AFII start, min HDAFII - 47, TDAFII at LO Level both SGs H/A 600 TDAFIIP 200/SG HOAFIIP 200/SG 10 For HOAFII, LOOP on sequencer is 47 sec.

TDAFII starts at nominal 17X in both SGs HDAFII control valves are normally open and throttle closed to controL flow between 200.230 gpm HOAFIIP valves arc 3 Rockwell model II A4006JKHY stop check valves.

TDAFII controL valves (4297, 4298) are 3 Fisher g470-HS.

SBLDCA assIInes 200 gpm per SG with thc failure of one DG 4.0 Hain Stets'ystem (HS)

Location (and elevation) of condenser dump valves and atmospheric relief valves Full load stcam line prcssure drop, psi HS Isolation valve close time (fuLL open to full close] close time, sec HS Isolation valve Cv [flow is f(dP))

CSD - elev 256'.875 ARV - elev 289'.563 approx 45 HSIV 5.0 check valve - 1.0 HSIV - 23500 check valve - 17580 This estimate, to thc governor

valves, is provided for comparison purposes only.

The check valve is assumed to close in 1 sec under reverse flow.

Hain Stern Code Safety Valves Number of vaLves (4 pcr linc)

Valve flow capacities

- Total, ibm/hr Valve Flow vs SG pressure (psia),

total per bank (4 valves)

, ibm/sec.

Humber of valves in bank 8

6621000 1110 1115 1120 1125 1131 1136 1141 1151 1161 1166 1173 1181 1190 1200 1205 1209 1211 0

40 91 141 191 222 223 225 227 228 342 494 646 799 859 920 931 Rated flow (3X accunulation pcr ASHY,Section III):

1085 psig................

797,700 ibm/hr (each) 1140 psig.....

~ ~..........

837,600 ibm/hr (each)

(

Valve setpoint(s), (first/last three),

nominal, ps Ig Valve blowdown characteristic 1085/1140 15X max 1m'alves are Crosby PHA-65 6R10 Setpoint tolerance is +1X / -3X.

Hodel valve setpoint at 1.01 (nominal),

and full flow at 1.04 (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 Atnospheric relief valve sctpoint/Air-operated, psig Atmospheric relief valve setpoint/gooster, psig Atmospheric relief valve capacity, ibm/hr 2

1050 1060 313550 at 1060 psig During Hot Standby operation setpoint is lowered to control no load Tavg Max flow is 380000 5.0 5.1 Turbine Generator (TG)

Corxienscr Ho. of condenser dwp valves Condenser dwT> valve open time, sec Condenser dump valve close time, sec Condenser dump valve setpoint(s)

Condenser dump valve Cv (flow is f(dP)]

For TT: Tavg>555 4 valves,

>563 4 valves; no TT: Tref +12 4 valves, Tref+20 4 valves Assuning close time = opening time On TT valves control open at 6.7X/F (PID) above 547 with full open sctpoints as described.

On 10X step load decrease same ratio with a 6F dcadband from Tref Design Cv (240) from design conditions (302,500 ibm/hr sat stcam at 695 psig) c 6.0 Chemical and Vol~ Control System (CVCS)

CVCS capacity/pump CVCS minimum/pump, gpm Type of controller (c.g.,

P + i) and gains 3 pwps, 60 gpn max each 15 PID 100X,180 sec,10 sec 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 6.1 Reactor Makeup Mater System (RMM)

RMM capaci ty/punp 2 pumps, 60 gpm each 7.0 7.1 7.1.1 Emergency Core Cooling System (ECCS)

ECCS Delivery vs RCS Pressure Residual Heat Removal (RHR) Delivery vs RCS Pressure Minimm RKR Delivery, train failure RCS Prcssure (psia) 155 152 150 140 120 100 80 60 40 20 14.7 Delivery (gpm) 0 0

0 250 648 836 985 1115 1232 1338 1365 LOCA Appendix K case.

Train failure results in one pwp running with 10X degradation with one line blocked.

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 line blocked RCS Pressure (psia) 155 154 152 150 140 120 100 80 60 40 20 14.7 Delivery (gpm) 0 0

160 252 516 830 1056 1243 1406 1552 1686 1720 LOCA Appendix K case (offsitc power available).

Two pumps running with 10K degradation with one linc blocked.

7 1.2 Safety Injection (SI) Delivery vs RCS Prcssure Hinimun SI delivery, 2 ixmps operating, one line spilling Press (psig) 1375 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0

Delivery (gpm) 0.0 62 125 167 201 229 253 273 289 305 321 336 352 368 394 Spill (gpm) 465 465 465 465 465 465 465 465 465 465 465 465 465 465 465 LOCA Appendix K case.

Train failure results in two ixmps running with 5X degradation with one line'"spilling to contairment.

Hinimua SI delivery, 3 pumps operating, non-LOCA Press (psi 1390 1315 1215 1115 1015 915 815 715 615 515 415 315 215 115 15 Delivery a)

Loop 'A l8 I 16 87 147 193 231 266 297 325 352 377 400.

423 445 465 485 (gpm)

Loop 19 97 163 214 257 295 329 360 390 418 444 469 493 516 538 Used for non-LOCA transients, 5X pulp degradation 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 (psia)

Delivery (gpm)

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

Haximua Si delivery, 3 pumps operating, SGTR 1390 1315 1215 1115 1015 915 815 715 615 515 415 315 215 115 15 Press (psig) 1375 1300 1200

=

'1100 1000 900 800 700 600 500 400 300 200 100 0

IBI 8

69 121 162 197 228 255 281 305 328 350 370 390 409 427 Loop A (gpm) 76 128 180 221 258 290 320 348 374 398 421 443 464 485 504 8

71 126 169 206 239 269 296 322 346 369 391 412 432 452 Loop B (gpm) 84 141 198 245 285 321 354 385 413 440 466 490 514 536 558 The KYPIPE model assunes no pump degradation.

Loop A and B'pressures are set equal.

Used for SGTR.

7.3 Acauulators Number of accunulators Total volune, each, ft Liquid voluae, ft

- min/max Liquid volune, ft

- Best Estimate initial pressure, psig - Kinimun / Haxisun initial temperature, F

Boron concentration, ppm (min/max) 2 1750 1126/1154 1140 700/790 105 2100/2600 LBLOCA Note -

EO analyses use a maxisxIa concentration of 3000 ppm 7.4 RMST RUST Temperature, min / max, degrees F

Hinimua RIIST volwe, gal RUST boron concentration, ppm (min/max) 60 / 80 300,000 2300/2600 Note -

EQ analyses usc a maximm concentration of 3000 ppm 8.0 Contairaent Initial containment pressure, psia min - 14.5 max - 16.7 Hinimua is used for LOCA analysis.

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) degrees F

Initial relative hunidity, X SM temperature min/max, degrees F

Haximun containment

leakage, wtX/day 90/120 20 35/80 0.2 LOCA teaperaturc lower for PCT calculations.

SLB higher for containment integrity 8.1 Contairwent Heat Sinks Listing of Passive Heat Sinks, quantities, materials, and configurations see HSTL 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 0.81 BTU/hrFft 31.5 BTU/ft F

note: minimsa conductivity corresponds to maximm density, and mexican conductivity corresponds to miniaua density.

(Qs Steel density, conductivity, capacity Stainless steel density, conductivity, capacity Containment free volune, min / max, cu. ft.

Ground Teeperaturc (degrees F)

Outside Air Temperature, min / max, degrees F

HTC for outside surfaces 490 Ibm/ft'8 BTU/hrFft 54.4 BTU/ft F

496 Ibm/f t'5 BTU/hrFft 54.6 BTU/ft F

1,000,000 / 1,066,000 55

-10 / 100 1.65 BTU/hr ft degrees F

below grade temperature Contairment fan cooler performance Tarp (deg F) 120 220 240 260 280 286 Hin Hax (X106BTU/hr) 2.05 4.55 35.1 99.2 40.8 113.8 46.8 129.3 52.9 145.5 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 CRFC delay, offsitc power not available, seconds Containment

Spray, 1300 gpm each pump, maxima

delay, sec Contairrncnt Spray, 1800 gpm each pmp, mininun

delay, scc Contairmcnt Design pressure, psig Distance Basement floor to Springline, feet Distance Springline to top of dome, feet 34 28.5 - one purp 26.8 - two purps 9 / (14 w LOOP) 60 95 52.5 includes 2.0 sec SI delay includes 2.0 sec SI delay This delay is from the time Contairwent Hi-Hi sctpoint is reached. It includes instrunent delay and spray linc fill time.

This delay is from thc time of brcak.

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 Pressurizer pressure and level algorithms SG secondary Level algorithm H/A H/A H/A Tavg ranps linearly from 547 degrees F at OX power to 561 degrees F at 100X power Pressurizer pressure sctpoint is constant at 2235 psig. Pressurizer level ramps from 35X to 50X for 0 to 100X power (547 561 degrees F) ~

Level remains constant at 52X to 100X power.

(Power from turbine 1st stage press.)

10.0 10.1 10.1.1 Safety System Setpoints Reactor Protection System Power range high neutron flux, high setting nominal accident analysis delay time, sec 1.09 1.18 0.5

/

0.1.2 Power range high neutron flux, low setting nominal accident analysis delay time, sec 0.250 0.350 0.5 10.1.3 Overtcmperature delta T

nominal accident analysis delay time, sec 10.1.4 Overpower delta T

nominal accident analysis delay time, sec Variable Variable 6.0 Variable Variable 2.0 Total delay time - fram the time the tecperature difference in the coolant loops exceeds the trip setpoint until the rods are free to faLL Hot explicitly modelled in safety analysis 10.1.5'igh pressurizer pressure nominal, psig accident analysis, psia delay time, sec 2377 2410 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 accident analysis, psia delay time, sec 1873 1775 (non-LOCA) 1715 (LOCA) 1905 (SGTR) 2.0 10.1.7 Low reactor coolant flow nominal accident analysis delay time, scc 91X of normal indicated flow 87X per loop 1.0 10.1.8 Low-low SQ level nominal accident analysis delay time, sec 17X of thc narrow range level span OX of narrow range level span 2.0 Hhile trip sctpoint could bc as low as

16X, AFM initiation limits to 17X 10.1.9 Turbine Trip (low fluid oil pressure) nominal, psig accident analysis delay time, scc 45 H/A 2.0 Hot explicitly modeled in safety analysis 10.1.10 Unde rvoltoge

nominal, V

accident analysis delay time. sec 3150 1.5 Safety analysis asswes RCCAs arc released 1 '

scc. after setpoint is rel cased.

10.1.11 Under frequency

nominal, Hz accident analysis delay time 57.7 57.0 1.2 Analysis is performed but not explicitly modeled in safety analysis.

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

10.1.12 intermediate range

nominal, RTP safety analysis, RTP delay time, sec 0.25 N/A Hay fluctuate due to core flux Hot explicitly modclcd in safety analysis 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 accident analysis, cps delay time, sec 1.4E+5 1.DE+5 2.0 Highest nominal value 10.1 14 Hfgh Pressurizer level nominal accident analysis delay time, sec 0.90 0.938 2.0 10.2 10.2.1 10.2.1.1 Engineered Safety Features Actuation System Safety Injection System High contafrmcnt prcssure Noninal setpoint, psig Accident Analysis setpoint, psig Delay time, sec 4.0 34 44 w/ LOOP

• only modeled in accident analysis for start of contafwent fan coolers.

Time delays are for start of contaiment fan coolers.

10.2.1.2

(

Low pressurizer prcssure Nominal setpoint, psig Accident Analysis sctpoint, psia Delay time, sec 1750

1785, SGTR

1730, non-LOCA

1715, LOCA 2.0 10.2.1.3 Low stcam linc prcssure Hominal setpoint, psig Accident Analysis setpoint, psig Delay time~ sec 514 372.7 2.0 Sce NSIL Sec HSCL 10.2.2 Contalreent Spray Hominal Setpoint, psig Accident analysis sctpoint, psig Delay time, sec 28 32.5 28.5 Sec NS8L Delay time includes time to fill lines.

See NS&L 10.2.3 AFM System Low-low steam generator water level Nominal Setpoint Accident analysis setpoint Delay time, sec 17 X of narrow range instrunent span each stcam generator 0 X of narrow range instrunent span each steam generator 2.0 A positive 11X error has been included to account for the SG level measurement system at a containment tecperaturc of 286 F

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 10.2 4.1 Steam Line Isolation High contairwent pressure Nominal Setpoint, psig Accident anaLysis setpofnt Delay time 18 H/A H/A Not explic>tly modeled Not explicitly modeled 10.2.4.2 High steam flow, coincident with low Tavg and SI Nominal Setpoint Accident analysis setpoint Delay time 0.466 Lb/hr equivalent steam flow at 755 ps'ig and Tavg <

545 F

H/A H/A Note: flow setpoint is below nominal full power flow and therefore this portion of logic is made up at power Hot explicitly modeled 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 Accident analysis sctpoint Delay time 3.6E6 lb/hr equivalent stcam flow at 755 psig H/A H/A Hot explicitly modeled Hot explicitly modeled.

Steam Linc isolation is assumed concurrent with SI (i.e. 2 s delay + 5 s valve stroke)

'10.2.5 10.2.5.1 11.0 Feedwater isolation High steam generator water level NominaL Sctpoint Accident analysis setpoint Delay time 8WI Ste~ Generators Heat load per SG, BTU/hr Primary flow per SG, Klb/hr Steam flow pcr SG, lb/hr (clean, unplugged)

Secondary design pressure, psig Secondary design teaperature, F

Haximsn moisture carryover, X

Narrow range lcvcl tap locations, inches above TS secondary face Wide range level tap Locations, inches above TS secondary face 85X of the narrow range instrunent span each SG 100X of the narrow range instrunent span each SG 2.0 2,602,000,000 PluggingX Flow Klb/hr 0

34950 5

34630 10 34280 15 33850 3,264,358 at 877 psia 1085 556 0.10 386 /a / 529 /e 8 /~ / 529 /e Instrunent loop only Design flows at T,~ = 573.5 F

Conditions for T.

= 573.5 F

1.1 SG Pressure Drops COLR Cycle 26, Revision 1

I f

e

Table 3,:

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

Secondary nozzle to nozzle dP Q fuLL power, psi Secondary nozzle to nozzle dP Q full power, psi Primary nozzle to nozzle unrecovcrable pressure drop vs. plugging, psi 14.7 7.5 PluggingX ap psi 0

31.01 5

33.27 10 35.82 15 38.72 Value is totaL static pressure drop.

Pressure drop from top of U-bend to outlet.

See associated flows for X plugging.

11.2 SG Tubes Ho. of tubes pcr SG Tube 00, inches Tube average wall thickness, inches Haxirrnmr tube length, ft Hinirlmr tube length, ft Average length, ft Hinimun U-bend radius, inches Kaximun U-bend radius, inches U-bend radius of shortest tube(s),

inches Average U-bend radius, inches Tube straight length (one side) above secondary

face, inches (min/max/average)

Secondary heat transfer area, ft* per SG Primary heat transfer area, fthm per SG Overall bundle height, ft above secondary face of TS 4765 0.750 0.043 70.200 55.925 61.988 3.979 54.007 4.044 24.51 303 /rn / 310 /i / 308.182 54,001 47,809 30.427 Includes length in tubcshect (2x25.625")

includes length in tubeshect (2x25.625")

includes length in tubesheet (2x25.625")

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

Tube material SG Tube Haterial Thermal Conductivity, BTU.in/hr-ftz-F SG Tube Haterial Specific Heat, BTU/lb-F Distance from top of tube bundle to 33X HRL, ft SB-163 Tarp F

200

,300 400 500 600 Tarp F

200 300 400 500 600 Alloy H06690 Conductivity 93 100 107 114.5 122 Conductivity 0.112 0.1155 0.119 0.1225 0.126 5.703 11.3 11.3.1

(

SG Voluncs SG Secondary Side Volunes Secondary volunc, ft (total)

Secondary volune up to lower NRL tap, ft Secondary volunc up to upper HRL tap, ft 4512.7 1893.2 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-bend inside shroud), ft*

Secondary riser voiuae, top of U-bend to spill.

over point, fta 1281.8 507.0 Equivalent to LOFTRAN riser volune.

11.3.3 Dmncomcr Vol~

Downcomer volune, top of TS to top of U-bend, ft Downcomer voluae, top of U-bend to spill-over

point, fthm 359.6 1437.3 11.3.4 SG Primary Side Voluaes Inlet plena per SG, ft*

Outlet pienun per SG, ft Tube primary voluae per SG, ft'rimary total voluac pcr SG, ft Circulation ratio (100X power, clean, unplugged)

Tubesheet thickness, inches 129.65 129.65 710.3 969.6 5.39 25.625 Circulation ratio = bundle flow /

steam flow.

Assunes 40,000 Ibm/hr b lowdown.

Includes cladding.

11 4 SG Primary Side Dimensions Primary head radius, inches Divider plate thickness, inches Inlet and outlet nozzle, inside diameter cylindrical section, inches Nozzle divergence angle, degrees Nozzle inside diameter at pienua, inches Nozzle lengths, inches Neigth from SG primary head bottom (outside) to top of TS, inches Distance tube shcct primary face to hot leg centerline, ft 58.375 1.875 31.200 11 30'7.0 cylindrical section conical,section total length 9o'/io 6.654 8.75 13.0 21.75 Radius to clad surf acc.

(

11.5 SG Secondary Side Dimensions Lower shell inside diamctcr, inches Lower shell thickness, inches Tube shroud inside diamctcr, inches Distance top of tube bundle to top of steam

nozzle, inches Steam nozzle flow rcstricter area, ftz Distance secondary face of TS to ccntcrline of fecdwater nozzle, inches 122 2.875 114 298.5 1.4 407 /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 feed ring, inches Cross. sectional area of tube bundle, ft Distance top of tube bundle to spilt-over point, inches Primary side roughness, micro-inches 374 41.64 178.0

Hozzles, head 60 Tubes 60 This value is totaL area inside shroud.

This value is equivalent to thc riser height for the OSG.

Values given are conservative assumptions.

11.6 SG Secondary Side Mater Hasscs Secondary water inventory, 100X power, T

573.5, no plugging, ibm Secondary water inventory, 100X power, T,~ =

559, no plugging, Lbm 86,259 liquid 5,286 steam 85,547 liquid 4,675 steam Best estimate vaLue Best estimate value.

11.7 SG Primary Side Head Loss Cocfficicnts SG inlet nozzle/plenums loss coefficient, ft/gpm~

SG outlet nozzle/plerwn loss coefficient, ft/gpm SG tubing loss coefficient, ft/gpm~

SG tubing loss coefficient, straight section (in), ft/gpm~

SG tubing loss coefficient, U-bend section, SG tubing loss coefficient, straight section (out), ft/gpm~

1.01E-09 for ID = 31.2" 3.31E-10 for ID = 31.2" 9.62E-09 for OX plugging 1.32E-08 for 15X plugging 4.19E-09 for OX plugging 5.73E-09 for 1SX plugging 1.02E-09 for OX plugging 1.40E-09 for '15X plugging 4.41E-09 for OX plugging 6.08E-09 for 15X plugging For tube ID ~ 0.664'<,

A = 11.458 ft', A,~~ 9.739 ft~.

Plugging is assumed to be uniform.

'For tube ID = 0.664",

A ~ 11.458 ft~, A<<c 9.739 ft~.

Plugging is assumed to be uniform.

For tube ID -"0.664<<, Ao= 11.458 ft', A,~>> = 9.739 ft'.

Plugging is assumed to be uniform.

For tube ID = 0.664", Ao= 11.458 ft, A,s= 9.739 ft.

Plugging is assumed to be uniform.

27 Cycle 26, Revision 1