ML20246L141

Provides Advance Changes to Be Included in Future FSAR Amend Re Component Cooling Water Sys Design Pressure

ML20246L141
Person / Time
Site:	Comanche Peak
Issue date:	08/31/1989
From:	William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-89630, NUDOCS 8909060254
Download: ML20246L141 (24)

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5 Lot' # TXX-89630 L

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905.4, 906.2 7UELECTRIC

$9j'9$$.2 Ref. # SDAR CP-89-005 eVulism J. CahiG, Jr.

August 31, 1989 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ADVANCE iSAR SUBMITTAL COMPONENT COOLING WATER SYSTEM DESIGN PRESSURE Gentlemen:

This letter provides an advance copy of changes to be included in a future FSAR amendment. These changes revise the Component Cooling Water System design pressure, In order to facilitate NRC Staff review of these changes, the attachment is organized as follows:

1.

Draft revised FSAR pages, with changed portions indicated by a bar in the margin, as they are to appehr in a future amendment.

2.

A detailed description / justification for the changes.

3.

A copy of the related SER section.

4.

A page containing the title of a " bullet" which consolidates and categorizes similar individual changes by subject and related SER section.

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August 31, 1989 ll3;-

4.Page 2 of)2, 5.

LThe bold / overstrike version of the revised FSAR pages referenced by-the detailed description / justification for the changes identified.

above.

The bold / overstrike version f acilitates review of the revision by highlighting each addition of new text in' bold type font and.'overstriking with a-slash (/) the portion of'the text that is-deleted.

1' Sincerely, if William J.

ahill, Jr.

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By:

Y Riig'e#b. Walker Manager, Nuclear Licensing

'JLR/vid-Attachment' 1c - Mr.'R.- D. Martin, Region IV Resident Inspectors, CPSES (3)

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Attachment to TXX-89630 August 31, 1989 Advance FSAR Submittal Concerning Revised Component Cooling Water System Design Pressure Item 1 Draft Revised FSAR Page 2 thru 8 Item 2 Detailed Description / Justification 9 and 10 Item 3 Related SER section 11 thru 14 Item 4 Bullet Title 15 Item 5 Bold /0verstrike Vers,on of Revised 16 thru 22 FSAR Pages 1

Page 1 of 22 1

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CPSES/FSAR 5ttachCGnt to TXX-89630; TABLE 5.4-8 Page.2 of 22 o

RESIDUAL HEAT REMOVAL SYSTEM COMPONENT DATA

Residual Heat Removal Pump

-Number 2-Design pressure (psig) 600 Design temperature (DF) 400 Design flow (gpm) 3800 Design head'(ft) 350 HPSH required at.3800 gpm (ft) 16 Power (hp) 400 Residual Heat Exchancer Number 2

Design heat removal capacity (Btu /hr) 39.1 x 106

-Estimated UA (Btu /hr 0F) 2.3 x 106 Tube side Shell side Design pressure.(psig) 600 165 DRAFT Design temperature (OF) 400 200 Design flow (1b/hr) 1.9 x 106 3.956 x 106 68 Inlet temperature (DF) 140 109.6 68 Outlet temperature (Or' 121.9 118.3 68 Material Austenitic Carbon steel stainless steel Fluid Reactor Component coolant cooling g.

water

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[Att'echGnt to'TXX-89630?

CPSES/FSAR

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Page 3 of_22_

= TABLE 6.2.2-1

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(SHEET 2)

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~ CONTAINMENT SPRAY' SYSTEM

'f0MPONENT DESIGN PARAMETERS 4.

-Containment Spray Heat Exchanger

-Quantity" 2

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. Type.

Shell and U tube Overa'11 heat transfer (8tu/hr'ft2 F) Coefficient 580.0 68 Flow. gpm 2; ell side-6080-Injection 5800 Recirculation 7200 Inlet-Temperature, F Shell side, maximum 135 Tube side, maximum 243 Design Pressure, psig

[ DRAFT; l[

Shell 165-

. Tube-325 Design Temperature. F Shell 200 Tube 300 Q-o 1't i

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Att:ch3:cnt to TXX-89630-TADLE 9.1-3

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-(Shret 2)

SPENT FUEL POOL COOLING AND CLEANUP SYSTEM MAJOR COMPONENT PARAMETERS Soent Fuel Pool Heat Exchancer Quant'"

(shared) 2 Design :.<at transfer, btu /hr 13.6 x 106 71 Shell Inha Design pressure, psig 165 150

. DRAFT Design temperature,"0F 200 200 Design flow, Ib/hr 2 x 106 1.80 x 106 Inlet temperature, OF 105 120 Outlet temperature, OF 111.8 112.5 Fluid - ci rculated Component Spent fuel cooling pool water water Material CS SS Soent Fuel Pool Demineralized Quantitu (shared) 2 i

Design pressure, psig 200 68 Design temperature, OF 200 Design flow, gpm 150 (maximum - 278) 76 Resin volume, ft3 50

~ Material SS Resin type Rohm and Hass Amberlite IRN-ISO or equivalent Draft Version

CPSES/FSAR-

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LAttach:;nt.to'TXX-89630' TABLE-9.2-2 p

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Paga-5 of'22 (Sh;et 1 of 2) k COMPONENT COOLING WATER' SYSTEM EQUIPMENT CHARACTERISTICS 1.

-Heat Exchanger.

Shell Side Tebe Stt:e Design flow, gpm.

14,700 14,000

. Design pressure drop, psi 12.4 5.3 Design pressure,-psig 165 150 DRAFT Design temperature, OF 225 225 Temperatures. OF*

Outlet 105.0.

108.4 Inlet 114.5 98.4 Design heat transfer rate 70 x 106 Stu/hr-Tubes-Material ASME 58-111 Type 706

2. Pumps Type Centrifugal. horizontal J 76 hilan Runout Capacity gpm 14,700' 16,400 Total Dynamic Head ft 226 210 NPSH, ft Minimum required 30 36 Available (minimum) 60 60 76 Design pressure, psig 165 DRAFT

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• Temperatures at design heat transfer condition

j' httach:Ignt to' TXX-89630 Page 6 of 22-TABLE 9.3-7 (Sheet 3)-

[

'Shell Side (Letdown)

Flow (1b/hr) 37,300 Inlet temperature (OF) 560 Outlet temperature.(OF) 290 Tube Side (Charaina)

Flow (1b/hr) 27.300 Inlet temperature (OF) 130 Outlet temperature (DF)~

518 Letdown Heat Exchancer Number 1

Heat transfer rate at design conditions (Btu /hr) 16.1 x 106 Shell Side Design pressure (psig) 165 DRAFT Design temperature (OF) 250 Fluid Component Cooling Water Material Carbon Steel

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httachdnt-toTXX-89630 CPSES/FSAR Page 7 of 22-TABLE 9.3-7 L

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-Shell Side Tube Side Desiti pressure (psig) 165 2485 DRAFT-Design temperature (OF) 250 650 Design flow (1b/hr) 129,000 12.410 Inlet temperature (OF) 105 560 Outlet temperature (OF) 145 165 Fluid Component Borated Reactor Cooling Water Coolant Material Carbon. Steel Austenitic Stainless Steel Seal Water Heat Exchanger Number 1

Heat transfer rate at design conditions (Btu /hr) 2.4 x 106 Shell Side Tube' Side Design pressure (psig) 165 150 DRAFT Design temperature (OF) 250 250 Design flow (1b/hr) 186,000 42,200 Inlet temperature (OF) 105 172 3-Outlet temperature (OF) 118 115

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' Attach::nt to TXX-89630 7 age 8'of'22-TABLE 11.2-3 1

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(Sheet 11)

L EQUIPMENT PRINCIPAL DESIGN PARAMETERS j

Components Earpat;n Heat Exchanaers

11. Reactor Coolant Drain Tank Heat.Exchangers Quantity Two Type U-tube Estimated UA, Btu /hr/F 70,000 Design Pressure, psig Shell 165 DRAFT Tube 240 Design Temperature, F Shell 200 Tube-200 Design Flow, Ib/hr Shell 112,000 Tube 44,600

• 'emperature (In), F Shell 105 Tube 180 i.

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[ Attachment 1toTXX-89630, DETAILED DESCRIPTION I

bl Page 9 cf 22

-j FSAR.Page p

<(as amended)

Group Rascription 1

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. Table S.4-8 2

Increas Seat exchanger design pressure shell side from 15L eo 165 psig.

Revision:

The heat exchanger shell side design pressure has been revised from 150 to 165 psig as a result of revised calculations. The revised calculation determined that this increase in design pressure will be high enough to prevent lifting the CCW system thermal relief valves in temporary pressure surge caused by the starting of the second CCW pump with one CCW pump in service. This increase in design pressure has no impact on pressure boundary components.

FSAR Change Request Number: 89-594.01 Related SER~Section: 9.2.2 SER/SSER Impact: No Table 6.2.2-1 2

See Sheet No(s):2 Increases heat exchanger design pressure shell side from 150 to 165 psig.

Revision:

Revises the heat exchanger shell side design pressure' (CCW System) from 150 to 165 psig.

See discussica provided for Table 5.4-8.

FSAR Change Request Number: 89-594.02 Related SER Section: 9<2.2 SER/SSER Impact: No Table 9.1-3 2

See Sheet No(s):2 Increases heat exchanger design pressure shell side from 150 to 165 psig.

Revision:

Revises the heat exchanger shell side design pressure (CCW System) from 150 to 165 psig.

See discussion provided for Table 5.4-8.

FSAR Change Request 'Jumber: 89-594.03 Related SER Section: 9. 2. '2 SER/SSER Impact: No h

Table 9.2-2 2

See Sheet No(s).1 l

Increases heat exchanger design pressure shell side 1.

from 150 to 165 psig.

Revision:

l Revises the heat exchanger shell side design pressure (CCW System) from 150 to 165 psig. See discussion provided for Table 5.4-8.

FSAR Change Request Number: 89-594.04 Related SER Section: 9.2.2 SER/SSER Impact: No l

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[At' tach:entto'TXX-89630 DETAILED DESCRIPTION Page 10.of'22-

- FSAR Page

~

(as amended)

Ar_gsgt Description Table.9.3-7 2

See Sheet No(s)':3,5 Increases heat exchanger design pressure shell side from 150 to 165 psig.

Revision:

Revises the heat exchanger shell side design pressure (CCW System) from 150 to 165 psig.

See discussion provided for Table 5.4-8.

r FSAR Change Request Number: 89-594.05 Related SER Section: 9.2.2 SER/SSER Impact: No

-Table 11.2-3 2-See Sheet No(s):11 Increases heat exchanger design pressure shell side from 150 to 165 psig.

Revision:

Revises the heat exchanger shell side design pressure (CCW System) from 150 to 165 psig.

See discussion provided for Table 5.4-8.

FSAR Change Request Number: 89-594.06 Related SER Section: 9.2.2 SER/SSER Impact: No 0-m u___

ittet.hment-toTXX-89630.

Page 11 of 22 The station service water system is designed to Quality Grog C and seismic Category I requirements.

Connections to other nonessential systems are-isolated by Quality Greg C seismic Category I valves that are normally shut. The valves to the fire protection system are locked closed.

Components of the syster are located in seismic Category I structures, which provide protection against-tornadoes tornado nonerated missiles, and floodi (see Sections 3.4.1 and 3.5.2 ofthisSER).

Stat / on service water system pipi between the pumphouse and the auxiliary butiding and between the auxiliary 11 ding and tte safe-shutdown impoundment is seismic Category I and is buried to protect the piping fra tornado missiles.

Pump motors, valve operators, and controls are located above the postulated level of the probable maximum flood in the seismic Category I pumphouse, which also provides tornado and tornado-aissile protection for systes components.

Thus,'the requirements of GDC 2 and the guidelines of Regulatory Guides 1.26, 1.29, 1.102, and 1.117 are met.

The station service water system is separated from the effects of internally generated missiles and high-and moderate-energy pipe breaks (refer to Sec-Sions 3.5.1.1 and 3.6.1 of this SER).

Pumps and pump motors inside the pump-house are physically separated free each other by walls designed to preclude coincident damage to redundant equipment free pipe reture, equipment failure, and missile generation. Thus, the requirements of GDC 4 and the guidelines of BTP A58 3-1 are met.

Thestationservicewatersystemoperatesduringnormaloperation$esystem therefore, it does not require additional periodic tests and inspection of t safety functions.

However, the components in operation are interchanged periodically to enable testing and inspection.

Recirculation loops are provided around the pumps for testing of these components.

Valves, controls, and instrumentation are also tested at mguiar intervals. The perfomence of the heat E+ t rs is sonitored periodically to detect excessive scale formation.

The system Is located in accessible areas to permit inservice inspection as required. Thus, the requirements of WC 45 and,46 are met.

Based on its review, the staff concludes that the station service water system meets (1) the requirements of WC 2,issiles, and environmental effects shar A 5, 44, 45, and 46 with respect to pro-taction against naturel phonemens, m ofassentialsystems;decayhostremovalcapability;inserviceinspectlonand functional testing; and (2) the guidelines of Regulatory Guides 1.26, 1.29, 1.102 and 1.117 and gTP A5B F 1 with, respect to the systems quality seiselc classification and protection against flood; tornado-missile, group and and pipe break effect. Therefore, itais at:ceptable.

9.2.2 Reacter Ammiliaries Cooling Water System (Component Coolirs Water Systan)

'i The componest cooling water system (CCWS) provides coo 11rg water to various plant camponents and rejects the heat to tie station service water system (refer to Section 9.2.1 of this SER). The CCWS is an intermediate cooling loop between radioactive or potentially radioactive heat sources and the ultimate heat sink water.

The CCWS provides cooling to the following essential plant auxiliary components during all modes of operation including postulated accidents (they are required for safe shutdown and accident sitigation):

containment spray pump heat exchangers, residual heat removal (RNR) pump seal coolers, safety-chilled-water system condensers, and control room air conditioning condensers.

9-9

" Attachment to TXX-89630 Page 12 of 22

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In addition, the CCWS cools the RHR heat exchangers during nomal shutdown and postulated accidents; it also cools the containment spray heat exchangers during postulated accident conditions.

Cooling is also supplied to the following non-essential components during nomal shutdown, nomal operation and refuel' ng:

hydrogen recombiner heat exchangers waste gas compressor seal water coolers positivedisplacementchargingpump,hydraul'ccouplingoilcoolerandlubeoll cooler, letdown and excess letdown heat exchangers, reactor coolant pump seal water heat exchangers, spent fuel pool heat exchanger boron recycle evaporator, wasta evaporator, floor drain evaporator, reactor coolant t> umps, reactor coolaat-drain tank heat exchanger, ventilation chillers, letdown c1111er, instrument air compressor and aftercooler, and process sample coolers.

Each reactor unit has a separate and independent CCWS..The system associated with each reactor unit has two redundant, full-capacity safeguards cooling loops and one nonsafeguards cooling loop.- The safeguards loops can be isolated from the nonsafeguards loop by redundant, automatically actuated motor-operated valves.

The interconnections between Unit 1 safeguards loops and Unit 2 safeguards loops are blocked by redundant locked-closed isolation valves. The nonsafeguards loop of each unit is connected to,the nonsafeguards loop of the other unit so that certain common components such as the spent fuel pool heat exchangers can be cooled by the CCWS of alther unit.

The nonsafeguards loops are noma,lly separated from each other by at least one' closed valve. Unit separation is maintained during postulated accident conditions by the redundant automatic valves, which isolate the nonsafeguards loop from the safeguards loop. There is no sharing of any safeguards component or safeguards function between the two units.

hus, the requirement of GDC 5 are satisfied.

The CCWS for each reactor unit has two full-capacity pumps and heat exchangers

. ith one puuni running during normel operation to cool the nonsafeguards loop-w and one of tto safeguards loops.

The,other pump and heat exchanger remain on stancgry during normal operation. Heat to removed from the operating CCWS heat exchanger by the corresponding train of the station service water systas.

The CCWS is maintained at a higher pressure than the station service water system to prevent inlaskaps of station service water which could cause chloride-induced stress corrosion. A partitioned surge tank wIth separate lines free each side of the tank to the suction of each of the component cooling water (CCW) peps is provided for each unit. The partition is designed to maintain its integrity wit) one side of the s tank empty.

The surge tank provides CCW pump not positive suction head system makeup water enouffements and accommodates expansion,and contraction of the system volume.

Makeup to the su tank is normally provided by the nonsafety-related demineralized water sys As a backup, tm seismic Category I, Quality Group C reactor makeup water system

)

will supply the CCW surge tank automatically upon receipt of a tank low-low level signal. A nonessential, normally isolated chemical feed is provided on the recirculation Ifne of each CCW pump.

Radiation monitors are provided on the return lir.n to each CCW pump. These radiation monitors are designed to actuate an alare in the control room on high activity level and close the CCW surge taak and drain tank atmospheric vent valves.

One CCW pump and heat exchanger are used per unit during normal operation to cool the nonsafeguards loop and one of the safeguards loops.

The design cool-i down rate for normal cooldown is achieved using both pumps and heat'exchsngers 9-10

- Attachment'to TXX-89630 PagQ.13 of 22 but only one pump and heat exchanger need be operable for an acceptable but slower rate of cooldown.

In the event of an accident, the stan6y CCW pump is started so that both safeguards loops will be cooled.

However, only one CCW pump.and heat exchanger is needed because the safeguards loops are redundant in that the components cooled by either safeguards loop can perform the minimum required safeguards functions.

Following containment spray isolation, the non-safeguards loop is ' isolated by r.edundant motor-operated valves.

The safeguards loops are isolated from each other by locked closed valvec or by redundant, automatically actuated motor-operated valves.

Each CCW pump and each safeguards loop is supplied with emergency power from separate emergency diesel buses.

The nonsafegbards loop can be isolated from the safeguards' loops by redundant motor-operated valves.

In addition, the portions of the nonsafeguards loop which are not seismic Category I are isolated from the remainder of the system by air-operat.ed valves which are designed to fail closed on loss of air supply.

The CCW flow to the reactor coolant pueps (RCP) would be blocked by a failure of one of the valves separating the safeguards loops from the nonsafeguards loop or by failure of the containment isolation valve in the single a v ly line to the reactor coolant pumps.

Component cooling water is provided to de RCP thermal barrier heat exchanger, pump motor air cooler and pump motor oil coolers.

Westinghouse tests have shown that on loss of CCW flow to the reactor coolant-pumps, the maximum recosmiended motor bearing temperature will be reached in about 10 min. The position of the va1ves separating the saf rds loop from the nonsafeguards loop is indicated by safety grade inst tion on the main control board.

Likewise, the applicant has verified by letter dated June 16, 1981 thatthecontainmentisolationvalvepositionIndicationissafetygrade andIslocatedonthemaincontrolboard.

In addition, the flow to each RCP upper bearing oil cooler, lower-bearing oil cooler, motor air cooler and thermal barrier cooler is indicated on the main control board with an alare provided<

for low flow.

Each pump motor is provided with five temperature sensors with indication on the main control board and alarms for high temperature.

Based on the quantity of instrumentation and the safety classification for the valve position indication, the staff concludes that the operator will have adequate indication of loss of CCW flow to the reactor coolant pumps and can take action to protect the plant before seizure of the reactor coolant pumps.

ThedesignoftheCCWSasdescribedaboveensuresthats tem function, with the exception of RCP cooling, is not lost assuming a si la active component failure coincident with a less of offsite power, and the the plant can be protected if RCP cooli is lost.

Adequate isolation is provided as indicated in the previene pa Thus, the requirements of GDC 44 are met.

The CCWS is hoseed in the seismic Category I auxiliary building,ich provide safeguards p

building, fuel building and reactor bu<1 dings (containments), wh protection against floods, tornadoes and tornado missiles (refer to Sec-tions 3.4.1 and 3.5.2 of this SER).

Essential portions of the systee are designed to seismic Category I Quality Group C requirements.

Thus, the requirements of GDC 2 and the pidelines of Regulatory Guides 1.26, 1.29, 1.102, and 1.117 are met.

t 9-11

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Attachment'to TXX-89630-Page 14~of 22 The component cooling water system is separated from the effects of internally generated missiles and high-and moderate-energy pipe breaks.

Each CCW Jump is located in a separate compartment in the auxiliary building.

Thus, t w requirements of GDC 4 and the guidelines of BTP AS8 3-1 are met.-

One CCW ptap per' unit is'normally operating.

i Availability of the stansky pump is assured by periodic functional tests and inspections as delineated in plant Technical Specifications.

The system is located in accessible areas to permit l

inservice inspection as required.

Thus, the requirements of GDC 45 and 46 are p

met.

'8ased on the above, the staff concludes that the component cooling water system.

meets the requirements of GDC 2, 4, 5, 44 45, and 46 (with respect to the system 3

Jrotection against natural phenomena, missiles, and environmental effects, decay i

wat removal capability, inservice inspection, and functional testing) and the guide]ines of Regulatory Guides 1.26, 1.29, 1.102 and 1.117 and BTP ASB 3-1 (with respect to the systems quality group and seismic classification and flood, tornado missile and pipe break effect protection).

Therefore, the system is acceptable.

9.2.3 Demineralized and Reactor Makeup Water System The nonsafety-related demineralized and reactor makeup water system is a single system designed to provide an adequate supply of deaerated demineralized water of reactor coolant purity ta other systems as makeup and to provide other plant demineralized water requirements for both units of the station. Wzter from onsite wells or from the surface water protreatment facility is used as influent to the systas. The system has no safety-related function.

Protection from flooding for safety-related equipment resulting from failure of the system is discussed in Section 9.3.3 of this SER.

Failure of any nonseismic equipment associated with this system will not cause any failure of safety-related systems or components. The system is capable of fulfilling the norssi rating require-monts of the facility for acceptable makeup water and is dost with the 1

necessary camponent ri-ty. Alatsed instrumentation has provided to prevent delivery of offspecification water to safety-related systems. Components of the demineralized and reactor makeu chemicals used throughout the system. p water system are compatible with allFa the capability to safely shut doun the plant as described above. Thus, the requirements of GDC 2 and 5 and the guidelines of Ppsition C.2 of Regulatory Guide 1.29 are met.

Based on its review, the staff finds that the system meets the requirements of g

GDC 2 with respect to the need for protection'against natural phenomena, meets the requirements of GDC 5 in regard to the effect of sharing in multiple unit facilities, and meets the guidance of Regulatory Guide 1.29 concerning its seismic classification.

Therefore, it is acceptable.

9.2.4 Potable and Sanitary Water System The nonsafety-related potable and sanitary water system provides clean water for human consumption and use, backup lubricating water for circulating water pumps, and water to supply circulating water chlorine evaporators. Water for the system is supplied by two deep we 1s, or alternatively, from the surface 9-12

7 Attach %njtoTXX-89630 lp,1

.Page 15'of 22 SECTION 9 - AUXILIARY SYSTEMS 9.2.2 Reactor Auxiliaries Coolina Water System (Connonent Coolina Water System)

SPLB

- 16.

.The FSAR has, revised the shell cide (CCW side) pressure of-l

.various heat exchangers.

i l-0 l

AttJich2:nt to: TXX-89630 d

TABLE 5.4-8

.P59e 16-of.22 l

u..

l RESIDUAL HEAT REMOVAL SYSTEM COMPONENT DATA Residual Heat Removal Pumo Number 2

Design pressure (psig) 600 Design temperature (OF) 400 Design flow (gpm) 3800 Design head (ft) 350 NPSH required at 3800 gpm (ft) 18 Power (hp) 400 Residual Heat Exchancer Number 2

Design heat removal capacity (Stu/hr) 39.1 x 106 Estimated UA (Btu /hr OF) 2.3 x 106 Tube side Shell side Design pressure (psig) 600 165 150 Design temperature (OF) 400 200 Design flow'(1b/hr) 1.9 x 106 3.956 x 106 68 Inlet temperature (OF) 140 109.6 68 Outlet temperature (OF) 121.9 118.3 68 Material Austenitic Carbon steel stainless steel Fluid Reactor Component coolant cooling g

water

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Attpch2;nt.to TXX-89630 CPSES/FSAR-Page'17 of 22' TABLE 6.2.2-1 (SHEET 2)

CONTAINMENT SPRAY SYSTEM COMPONENT DESIGN PARAMETEB1 4.

Containment Spray Heat Exchanger-Quantity 2

' Type Shell and U tube Overall heat transfer (Btu /hr ft2 F) coefficient 580.0' 68 Flow, ppa Shell side 6080 Injection 5800 Recirculation 7200 Inlet Temperature, F I

Shell side, maximum 135

-Tube side, maximum 243 Design Pressure, psig Shell 165 150 Tube 325 Design Temperature. F Shell 200 Tube 300 L

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CPSES/FSAR

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' Attach::nt to TXX-89630

. TABLE 9.1-3 2 *:

Page118 of 22' (Sheet 2)

SPENTFUELPOOLCOOLINGANiCLEANUPSYSTEM MAJOR COMPONENT PARAMETERS Soent Fuel Pool Heat Exchancer Quantity (shared) 2 l

Design heat transfer, btu /hr 13.6 x 106 71 i

Shell Inha Design pressure, psig 165 150 150 Design temperature, OF 200 200 Design flow Ib/hr 2 x 106 1.80 x 106.

~

Inlet temperature,'0F 105 120

' Outlet temperature. OF 111.8 112.5 Fluid circulated Component Spent fuel cooling pool water water Material CS SS Scent Fuel Pool Demineralized Quantity (shared) 2 Design pressure, psig 200 68 l Design temperature, af 200 Design flow, gpa 150 (maximum - 278) 76 Resin volume, ft3 50 Material SS l'

Resin type Rohn and Hass Amber 11te IRN-150 or equivalent l

l Amendment 71 May 77, 1988

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CPSES/FSAR 4ttachment.to TXX-89630 TABLE 9.2-2 Paga.19 of 22 P

(Sheet I of 2) n COMPONENT COOLING WATER SYSTEM EQUIPMENT CHARACTERISTICS-L

,1.

Heat Exchanger Shell Side Tube Side Design flow, gpm 14,700 14,000 Design pressure drop, psi 12.4 5.3 Design pressure, psig 165 150 150 Design temperature, OF 225 225 Temper 6tures. OF*

Outlet 105.0 108.4 Inlet 114.5 98.4 Design heat transftt rate 70 x 106 Btu /hr Tubes Material ASME SB-111 Type 706

2. Pumps Type Centrifugal, horizontal 76 Desian Runcut Capacity gpm 14,700 16,400 Total Dynamic' Head, ft 226 210 NPSH, ft L

Minimum required 30 36 Available (minimum) 60 60 76

. Design pressure, psig 165 150

• Temperatures at design heat transfer condition

._______A_

CPSES/FSAR-

.1

.htt,5chodnt to TXX-89630 TABLE 9.2-2 Pag 9 19 of 22 (Sheet 1 of 2) i COMPONENT COOLING WATER' SYSTEM EQUIPMENT CHARACTERISTICS 1..

Heat Exchanger Shell Side Tube Side Design flow, gpm 14,700 14,000 Design pressure drop, psi 12.4 5.3 Design pressure, psig 165 150 150 Design temperature, OF 225 225 Temperatures. OF*

Outlet-105.0 108.4 Inlet 114.5 98.4 Design heat transfer rate 70 x 106 Btu /hr Tubes Material ASME SB-111 Type 706

2. Pumps Type Centrifugal, horizontal 76 Desian Runout Capacity gpm 14,700 16,400 Total Dynamic Head, ft 226 210 NPSH, ft Minimum required 30 36 Available (minimum) 60 60 76 Design pressure, psig 165 150

• Temperatures at design heat transfer condition

f c...

' Attach cnt to'TXX'-89630 Paga 20 of 22 CPSES/FSAR F

TABLE 9.3-7.9

~

(Sheet 3)

Shell Side (Letdown)

Flow (1b/hr)-

37,300 Inlet temperature (OF) 560 i

Outlet temperature (OF.)

290 Tube Side (Charcino)

Flow (1b/hr) 27,300 Inlet temperature (OF) 130 Outlet temperature (OF) 518 Letdown Heat Exchanagt Number 1

Heat transfer rate at design conditions (Btu /hr) 16.1 x 106 Shell Sidt Design pressure (psig) 165 150 Design temperature (OF) 250 Fluid Component Cooling Water Material Carbon Steel 0:

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.Attachm:nt'to TXX-89630

[l'

'Page 21 of.22.

CPSES/FSAR TABLE 9.3-7

.(Sheet 5) ~

N Shell Sida Tube Side Design pressure (psig) 165 159 2485 Design temperature (OF) 250 650 n

Design flow (1b/hr) 129.000 12,410 1

Inlet temperature (OF) 105 560 Outlet temperature (OF) 145 165 Fluid Component Borated Reactor Cooling Water Coolant Material Carbon Steel Austenitic Stainless Steel Seal-Water Heat Exchanaer

. Number 1

Heat transfer rate at design conditions (Btu /hr) 2.4 x 106 Shell Side Tube Side 1

Design pressure (psig) 165 Ile 150 Design temperature (OF) 250 250 Design flow (1b/hr) 186,000 42,200 Inlet temperature (cF) 105 172 Outlet temperature (OF) 118 115

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.P:ga 22 of 22 TABLE 11.2-3

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(Sheet 11) l-EQUIPMENT PRINCIPAL DESIGN PARAMETERS Components Parameters Heat Exchancers 11; -Reactor Coolant Drain

-Tank Heat Exchangers Quantity Two Type U-tube Estimated UA, Btu /hr/F 70,000 Design Pressure, psig Shell 165 250

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Tube 240 Design Temperature, F Shell 200 Tube 200 Design Flow Ib/hr Shell 112,000 Tube-44,600 Temperature (In), F Shell 105 Tube 180 0

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