ML20064M062
| ML20064M062 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/09/1983 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| SBN-460, NUDOCS 8302150451 | |
| Download: ML20064M062 (17) | |
Text
SEABROOK STATION
% ONks:
1671 Worcesor Rood Fnunlacham, Mossochusens 01701 gggg (617).E72 3100 February 9, 1983 SBN-460 T.F. B7.1.2 United States Nuclear Reguletory Commission Washington, D. C. 20555 Attention:
Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444
Subject:
Open Item Response: (SRP 9.1.3; Auxiliary Systems Branch)
Dear Sir:
In response to the open item regarding the Spent Fuel Fool Cooling i
Subsystem, we have revised FSAR Sections 9.1.2 and 9.1.3 as delineated on the attached annotated FSAR Pages 9.1-3, 9.1-3a, 9.1-4, 9.1-5, 9.1-6, 9.1-7, 9.1-8, 9.1-8a, 9.1-8b, 9.1-9, 9.1-10, Table 9.1-1, Table 9.1-2, and Table 9.1-3.
The attached FSAR pages will be incorporated in OL Application Amendment 48.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY 1
00 J. DeVincentis 3
Project Manager ALL/fsf cc: Atomic Safety and Licensing Board Service List 8302150451 830209 PDR ADOCK 05000443 A
PDR 1000 Elm St.,P.O. Box 330, Manchester,NH O3105
- Telephone (603)669-4000. TWX 7102207595
ASLB SERVICE LIST Philip Ahrens, Esquire Assistant Attorney General Department of the Attorney General Augusta, ME 04333 Representative Beverly Hollingworth Coastal Chamber of Commerce 209 Winnacunnet Road l
Hampton, Nil 03842 William S. Jordan, III, Esquire Harmon & Weiss 1725 I Street, N'W.
Suite 506 Washington, DC 20006 E. Tupper Kinder, Esquire
/
Assistant Attorney General Office of the Attorney General 208 State House Annex Concord, NH 03301 Robert A. Backus, Esquire 116 Lowell Street P.O. Box 516 Manchester, NH 03105 Edward J. McDermott, Esquire Sanders and McDermott Professional Association 408 Lafaycete Road Hampton, NH 03842 Jo Ann Shotwc11 Esquire Assistant Attorney General Environmental Protection Bureau Department of the Attorney General One Ashburton Place, 19th Floor Boston, MA 02108
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Sg I & 2 Ame:dment 48 ygAg Jtnutry 1983 the fuel racks will preclude criticality resulting from placing a fuel element on the top of the rack. Crill work between rows of fuel racks provides psitions not designated a positive mechanical method of preventing insertion in p for fuel storage. Spaces between elements within the rach have physical barriera to prevent insertion of elements between fuel politions.
The new fuel storage facilities (storage vault and racks) are designed to maintain the fuel spacing during a safe shutdown earthquahe (SSE). All oismic Category I critical components (walls, racks) are designed to meet s requirements. (See Section 3.7 and Suhaection 3. A. A.)
The cusk handling crane and the spent fuel bridge and holot are designed Lea (CNAA) Speci-in compliance with Crane Manufacturer Association of Amer fication 70, " specification for Electric overhead Traveling cranes," 29CFR1910 and 29CFR1923 requirements. The cranas are not seismic Category I components; however, in compliance with Regulatory Position C2 of Regulatory Guide 1.29, the cranes design parameters are specified to provide adequate quality control of a DBE or S$g, of fabrication and control of design so that in the eveut the cranes will not fail in such a manner as to reduce the functioning of any plant feature designated as seismic Category I by Regulatory Guide 1.29.
The cranes are prevented from being dislodged off their rails during the SSE by mechanical anti-derailing devices. Figures 1.2-17 and 1.2-18 show the space envelope, boundaries and limits of hook travel of the cranes.
Spent Fuel Storage l
9.1.2 cks is to maintain The safety function of the spent fuel pool and storage ra L1 credible storage the spent fuel assemblies in a suberitical array during (
conditions, and to provide a safe means for cack loading Of the assemblies.
9.1.2.1 Design Bases The spent fuel pool storage facility is designek in accordance a.
with Regulatory Guide 1.13.
l b.
A total of 1206 fuel assemblies can be stored in the spent fuel I
pool. The spent fuel pool is able to accommoda':e 123f spent fuel and assemblies, based on sixteen (16) refuelings, one entire core, thirteen (13) extra spent fuel assemblies. Thi4 number of accom-i modated spent fuel assemblies is based upon the! following criteria:
1.
Six refuelings, each of which generates 65' spent fuel assemblies; Ten refuelings, each of which generates 64'-spent fuel Assemblies; 2.
fuel 3
One complete core unloading which generatek 193 spent assemblies; 1
i 4.
Thirteen spare locations if needed.
48 9.1-3 C926 - N011W15 M00dO935 Aw9 IGalt C8. 60*033 300*d
SB162 Amendmext 48 FSAR Jcau2ry 1983 Total fuel ~ssembly storage capability is based on fuel storage a
c.
cell geometry, center-to-center distance, lead-i.n angle requirements sad poison thickness.
d.
The spent fuel racks are designed for high densi ty fuel storage, and contain neutron absorbing material to assure a K,gg 6 0.95, j
even if the fuel is immersed in unborated water, 4e The design of the spent fuel pool storage racks is such that spent e.
designated locations, fuel assemblies cannot be inserted in other thei t
thereby preventing any possibility of accidents:, criticality.
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Amendment 48 sa 1 & 2 Jrnuary 1933 FSAR f.
A minimum of 10'-6" of water above the highest fuel element position is provided to permit fuel handling without exceeding a radiation T4e concrete walls dose of 2.5 ar/hr at the surface of the pool.
provide s%ste esMarinn pentaction from irradiated fuel assemblies.
The impact load for the design of the racks is b sed on a 17 x 17 g.
fuel assembly, 8.426 inches square, 167 inches 1 ng, weighing 1467 pounds, and falling a distance of 18 inches to t a racks at the l+a worst possible orientation._ _
M h.
The facility and the building in which it is houJed is capable of withstanding the effects of extreme natural p!sencuena, such as the SSE, tornadoes,1:,urricanes, missiles and i'loods.
I 1.
The spent fuel storage racks have been designed '
to withstand an SSE, impact, handifag loads, and dead load of the fuel assemblies, and meet ANSI N18.2 requiresents.
3.
The pool walls, fuel storage racks and other cri tical components whose failure could cause criticality, loss of c0oling or physical i
damage to fugl, are classified as seismic Category I.
k.
Failure of non-safety-related systems or structures located in the vicinity of the spent fuel storage facility which are not designed to seismic Category I requirements will,, not. cause an increase in Kefg to exceed the maximum allowable:.
1.
The spent fuel pool b' ridge and hoist is designed to remain on its rails during an $$E and, therefore, cannot dhmage stored fuel.
l The crane handling system is designed to preventi excessive forces m.
- from being applied to the spent fuel storage racks.
9.1.2.2 Facilities Description The spent fuel storage and han!. ling facility consists of ur major areast
- 1) the spent fuel pool. 2) the fuel transfer canal, 3) the spent fuel cask loading area and 4) a decontamination area. This arrangement is shown in Figures 1.2-15 through 1.2-21.
fuel pool is a water-titled cavity designed to safely store irradiaevd The* spent fuel assemblies. This pool is constructed of reinforced chacrete, with all interior surfaces lined with stainless steel.
The fuel storage area is prote.. ed against external tornadio missiles by 2-foot thick reinforced concrete walls. The large roll-up door on the west l
wall of the fuel storage building is not designed for tornsdo missiles; 44 however, a missile vs11 is provided inside the building ec prevent any aissiles that could possibly penetrate the roll-ap door from reaching the storage pool or cooling equipment.
i 9.1-4 3
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SB1&2 Amendment 48 F5a January 1983 I
he ettvation of the rail car loadin ' area is 20'k".
Prc tection against a
flooding is assured since the pool operating floor level e levation is at 25'-0", which is above any postulated flooding conditions resulting from any potential pending on the site due to extreme rain and wave overtopping.
I The storage racks which hold the spent fuel assemblies arst'sodular units, and each unit is free stand'.ng.
l 48 A portion of the pool will be reserved for inspoetion and testing of spent fuel assemblies.
R e spent fuel pool is separated from the fuel transfer canal by a concrete shielding wall with a removable gate to facilitate the transfer of fuel a ssemblie s.
Location of the removable gate is shown on Figure 1.2-16.
he fuel transfer canal contains the necessary equipment to transfer the fuel assemblies to ar.d from the reactor containment. His equipment includeus
- 1) a fuel transfer system conveyor car; 2) fuel transfer i alve; 3) fuel transfer system lif ting frame equipment; 4) fuel transfor system control panels and 5) new fuel elevator. He operation of this equipment is discussed in Subsection 9 1.4.
Isolation of the fuel transfer canal from the spene fuel pool by the removable gate provides a means for dry maintenance of the raft. ling equipment.
I he cask loading pit is located next to the fuel transfer canal. This provides for submerged loading of spent fuel. h e location elimina tes the need to move heavy cask components over either net or spent fuel a corage areas.
De cask-handling crane is, located so that its path of tra, vel does not pass over the. spent fuel pool. H e cask is lowered in two stapet from the operating floor level of 25'to a shelf at elevation 4'-51s", and thet to the loading i
position on the boccos of the pool at elevation (-) 23'-1W".
This arrangement prevents submersion of the crane hook and cables in the pdol water and eliminates contamination of the crane.
t h e spent fuel assemblies are handled by a long-handled tdol suspended from an overhead hoise and manipulated by an operator standing lon the movable bridge over the pool. A minisaan of 10'-6" of water exised during fuel handling operations to provide radiation protection to the operacot.
We hoist on the spent fuel pool bridge is equipped with h load cell to advise the operator if the fuel assembly is caught in the ' storage rack.
his load cell has adquace sensitivity to detect an abnormal binding condition 9.1-5
85 1 & 2 FSAR If the [ load exceeds ai and thus prevent the movement of the entire rack.
preset limit of 2,500 lbs, the hoist control circuit is injterrupted and the brakes set.
The spent fuel cask decontamination area is used for the skorage, maintenance, This ar'ea can cleaning, and decontamination of spent fuel shipping casksi.
also be used for the temporary storage of other contaminacled components.
Se area is sized to permit the storage of a snipping cask; head, shipping cask, cask lif ting beam and a cask head lifting, device.
Decontamination and maintenance procedures may require thei use of portable scaf folds or elevated platforms to gain access to the uppee parts of the The decontamination area is previded with electricilty, plant air, cask.
fresh water, desineralised water, steam and adequate drai$se for the decon-This area is located between she transport vehicle tamination washdown water.
loading area and the cask loading pool.
The spent fuel pool is monitored for leakage by a series df leak detection The leak monitor system channels located adjacent to each liner seas weld.
ted in the fuel has three channels which will gravity drain to a sump locs His soning arrangement
- can be uset to aid in establishing storage building.
the location of the leakage. By monitoring the leakage rdte, any change in the integrity of the liner can be established.
9.1.2.3 safety 2 valuation the required margin of soberiticality of the fuel storage { array is assured by neutron absorber material built into the storage structure of the rack.
the fuel pool and storage racks are designed so that noradt loads, when t
combined with the forces resulting from the SSE, will not' result in failure.
The spent fuel pool, fuel transfer canal and cask loading;pic are designed Seisnie design censiderations of to meet the requirements of ACI 318-71.
these areas are discussed in detail in section 3.7 and subsection 3.8.4.
I The opent fuel pool cooling pWap suction penetration is 14cated approximately two feet below the water level elevation, and the return line is a minimum top of the spent fuel assemblies. The failure of piping
,.5 16 feet above the externdt to these penetrations will not result in lowerind of the pool waear The amount of water remaining above the top of the below this elevation.
fuel assemblies is approntmately 16 feet, and this will rdault in a pool surf 4ce radiation level of less than 2.5 ar/hr.
The cask loading pool and the spent fuel pool are ' separate pools. A loss fuel pool water from a cast drop accident is pretented-by an 4aolation of spent gate, protected from the cask by concrete walls, which is installed between fuel pool and the transfer canal during cask handling operations.
the spent jhecranecannot See Figure 1.2-17 for the limits of travel of the cask.
9.1-6 1946 - NO1101S t od8W35 AW9 CSitt C8. 60*G33 908 N S-3 sm w
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8B1&2 Amendesst 44 FSAR February _1982 be passed over the spent fuel storage areal hence the fuell shipping cask cannot be transported over this area. Hence, dropping of a heavy cask will not breach the integrity of the spent fuel storage area nur damage stored fuel. The cask travels over the cask handling dry storage area as it travels from the receiving trea to the cask loading pool. The spent fuel cask cannot travel over any safaty-related equipment.
Protection assinst the effects of tornado and wind loadihn is discussed in seccion 3.3.
Protection against the dynamic effects associated with postulated pipe ruptures is discussed in Section 3.,6.
Raidiation monitoring is discussed in Section 12.3.
9.1.3 spent Fuel Fool Cooling and Cleanup syst_es 9.1.3.1 Deslan Bases the functions of the spent fuel pool cooling and cleanup isystem are tot Continuouslyremovedecayhastgeneratedbyfudielementsstored a.
in the pool, b.
Continuously maintain a minimum of 10 feet of deter over the spent fuel elements to shield personnel, and l44 Continuouslymaintainthechemicalparameteradadopticalclarity l
c.
of the spent fuel pool water, and the water in ithe reactor cavity 44 and refueling canal during refueling operationd.
Each of the two units has an independent spent fuel pool: cooling and purificatica system, and no interconnections exist between the two units.
All portions of the spent fuel pool cooling loop are designated Safety Class 3,andaredesignedandconstructedtomeetseismicCateforyIrequirements.
Those portions af the etaanisp synene net designed en these ragsnirementa are normally isolated from the cooling toep.
A teak detection system is previded (refer to subsection!.1.2).
9 All safety-related portions of the spent fuel pool cooling system are housed in structures capable of withstanding seismic and flood donditions, as well tornado generated missiles. Refer to section 3.5 foria discussion of asinternally-generated missiles and jet Impingement. Prot 4ction against dynesic affects associated with postulated pipe ruptures is disc 4ssed in section 3.6.
A seismic Category I normal makeup and a backup supply cipable of being connected to an alternate seismic Category I source are provided.
The sp mt fuel pool cooling system is designed to assure. adequate cool *.ng to stored fuel, assuming a single failure of an active cesponent coir.cident with a loss of offsite power.
9.1-7 6
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83 1 & 2 hsendment 48 F' GAR January 1983 The spent fuel pool cooling and cleanup system design temprature is 200*F, with a design pressure of 150 psig.
The systes design has been evaluated using the NRC Branch Technical Fosition Ass 9-2.
he basic assumptions used in this analysis are as follows:
1)
The reactor core heat output is 3411 Mirt.
2)
Full power operation is assumed for the entire fear between annual refueling.
3)
The fuel is unloaded annus11y with approximatelf one-third of a core transferred to the spent fuel p J1 for 16 tefueling cycles as depicted in Subsection 9.1.2.1b.
The spent fuel pool inventory considers a full core to be placed in the spent! fuel pool 36 days 4
after the 16th refueling.
4)
The irradiation time for the first cycle refuel na batch is 365 days; for the second cycle 730 days, and for the equilibrium cycles 1095 days. An average fuel assembly power of IP.67 MWT is.nsed for all irradiation times. For the full core unload, 36 days after the 16th refueling, one-third of the core was irradiated for 36 days, one-third has been irradiated 401 days, add one-third has been irradiated for 766 days.
51 The time sequence used for full core unload is 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> to prepare for refueling the reactor and the full dora unload.
The analysis using the above assumptions, and the computed code DgsgX(1)
' yields the following' maximum decay heat loads in the spent fuel pool.
Spent Fus: Fool -
Max'*-- Decay l leat-STU/RR
,Refuelina Cycle At End of lla fuelina 6
1 11.51
- 10 2
12.92 x 106 13.78 x 106 3
4 14.33 x 106 5
14.75 x 106 6
15.11 x 106 15.45 x 106 7
15.78 x 10e 8
16.09 a 106 9
16.40 x 106 10 11 16.69 x 106 16.98 x 106 12 13 17.27 x 106 l
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-F8AR January 1983 14 17.54 xl.106 15 17,81 :1G6 16 18.08 x! 106 Full Core 36 days af ter 16th esfooling 42.6 x i106 l
Presently, the sfaces thermal design provides for the reshal of 18.1 x 106 81V/HR of decay heat while maintaining a pool water temperkture of 1220F if 16 refuelings of 1/3 core each are to.be acconnodated. Iniaddition, the 6 BTU /HR of liecay heat and a present design allows the removal of 42.6 x 10 pool water temperature of 1410F if the heat load is produced from 16 refuel-ings and an entire irradiated core. The values of 1220F and 1410F are valid only if all of the spent fuel heat exchangers and pumps arls operating during the heat removal process (refer to Table 9.1-3).
The computer code BUTREg(2) is used to calculate the translient temperature response in the spent fuel pool. SeeTable9.1-3foradtftionalsystem thermal design conditions.
The final storage capacity of the spent fuel rack will be 1236 fuel elements.
This accepts the 1223 spent fuel elements from the 16 refuelings plus a full core reload. The remaining 13 cella could be used for stcrage of fuel elements th,tt may be removed from the reactor between cycles because of cladding defects, As the heat load to the spent fuel pool is based upon the normal cycles etc.
and irradiation, the impact of partial spent fuel cells id the 13 additional cells is inherent in the total heat load calculation.
i System component design data, together with the safety and code class require-ments, are presented in Table 9.1-1.
9.1.3.2
System Description
TheflowdiagramsforthissystemareshowninFigures9.f-1and9.1-2.
fuel pool cooling and cleanilp system is comprided of three sub-gach spent systems:
Spent fuel pool cooling subsystem Spent fuel pool cleanup subsystes geactor cavity and canal cleanup subsystes 9
9.1-8a 7
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as1&2 Amendment 48 j
January 1983 FSAR The overall system is comprised of the following major costponentes Two spent fuel pool cooling pumps Two spent fuel pool cooling heat exchangers One iclet strainer one pre-filter one dominaraliser i
One post filter i
One skimmer pump t
i Five spent fuel pool skimmer intakes One reactor cavity cleanup pump w
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55 1 & 2 Amendment 43 FSAR January 1963 Soent Fuel Pool Coolina subsystus s.
The spent fuel cooling pumps take suction from thi pool and circulate water through the heat exchangers which are cooled by the primary component cooling water system. Pool water enteral the suction linethroughastrainernearonewallofthepooljatapointthirteen feet higher than the return line terminations. W e return lines are located at a sufficient distance from the suct{ ion line to assure adequate circulation and uniform pool wate't' comparatures.
All system connections to the fuel pool penetrate at elevations suffic,tently above the top of the fuel (10 ft.) ec maintain adequate shielding in the event the water level drains to t,he penetration level. Piping arrangement precludes syphoning befow this level.
All components in contact with the spent fuel cooking water are stainless steel.
ThespentfuelpoolpumpmotorsareClass1Enotohsandaresupplied from separate emergency busses.
b.
Spent Fuel Fool __ Cleanup Subsystem spent fuel pool water quality is maintained by a pool skimmer loop which filters and demineralises the circulated water. The a skisser t sol skimmer loop consists of five pool surface shimmers,ilised pump, two filters and a domineraliser. This syston is ut to maintain the pool surface free from floating p4rticles and other saterials anJ to remove radioactive materials in the water.
The system is elsed to process approximatcly 120 hym, which esame that 1/2 of the pool. volume is processed in a day 6 All speat fuel pool cooling and cleanup system equipment is' located in the fuel storage building, except the filters and demIneraliser which are located in the desineraliser area of the priahry auxiliary building.
The skimmer pump motor is not Class 1E, and is supplied from a local control center.
c.
Reactor Cavity and Canal Cleanup System The reactor cavity cleanup portion of the system is designed to purify the reactor cavity during refueling operational to ingrove the optical clarity of the water. A composite drawing showtag this function is shown in Figure 9.1-2.
The systne consists of five surface skiassers at the water surfec'e of the refueling cavity and refueling canal, all piped to the suctiion'6f %he;reattor cavity cleanup system. The cavity water is pumpeld through the chemical and volume control system mixed bed demiberaliser and filters to the auction of the residual heat removial pumps ti..ere it is returned to a cold leg through a residual Neat removal hast exchanger. Suction can also be taken from day of the cavity drains and final cavity cleanup effected by pumpfng the cavity water through a portable cleanup filter.
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1 he reactor cavity cleanup pump motor is not Cla es IE, and is supplied from a motor control center in the cont rol building.
9.1.3.3 se fety Evaluacion Normally, more than 25 feat of water is maintained over the ' spent fuel.
=
During fuel handling operations, the operator is protected from direct shine least 10 feet of wated. The puritication emanating fros the spent fuel by at I
provided by the citanup sys ces, in addition to the water levels mai:cained 3
fuel, result in a pool surface radiation level of less than q
above the spent 2.5 ar/hr, which allows unlinited operator access to the furface of the 4
However, the filters,and the dmaineraliser pool and cooling system compocents.in the cleanup system and expected to collect particulatejand l
'l These components are u
active materials, and thus have restrictive access.
lls. A radiological tocated in the primary auxiliary building behind shield wa evaluation of the purification Icop is presented in Chaptors 11 and 12.
Each spent fuel pool pump is capable of circulating pool vater through either j
fuel pool heat exchanger.
If one spent fuel pool pusp becomes inoperable r
spent each heat exchanger for any reason, the remaining pump supplying half flow to can maintain pool water temperatures at 1350F, arith sixteen spent core regions stored in the pool.
fuel pool pump and heat exchanger are operable, the pool If only one spot water temperature can be maintained below 157of with 16 spent core regions in the pool (refer to Table 9.1-3).
4 i
o ne thermal capacity of the spent fuel pool cooling systek equals the physical storage capacity of the spent fuel pool. Thus, actual waker temperatures 2
will be no greater than those indicated in Table 9.1-3.
fuel pool cooling and cleanup system is designed so that the pool level will not be inadvertently drained below a point apphoximately 10 feet The spent fuel assemblies, he spent fukt pool suction above the top of the spent line penetration and the return line terminations are lockted at elevations such that the failure of piping external to these penetrations will not result in lowering the pool water level below this elevacLon.
fuel pool heat exchanger is supplied cooling water from a separate In the unlikely Each spent primary component cooling water loop (see Section 9 2.2).
the
[
event that all forced circulation cooling flow to the pool is lost, 280,000 gallone) provides a heat large volume of pool water (approximatelyThe minimum time' for the pool vater sink which allows time for maintenance.
to reach the saturation temperature is 2-3/4 hours for thit 16 spent core lg region storage condition.
fuel pool makeup water can be obtained from either the refueling water Spent The refueling scorage tank, or the condensate storage tank, if necessary.
A Water storage tank and its piping to the pool is seismic Category I.
hose connection is provided in the emergency feedwater puhp suction piping
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from the seisnie category I sendeneste eterage tank.
T V canaareian la 4
9.1-10
SB.1 &'2 l
Assendment 44 January 1983 FSAR i
TABLE 9.1-1 (sheet 1 of 2)
SPENT FUEL COOLING AND ggAwUF SYSTEM DESkCN DATA SYSTEM DESIGN DATA System Cooling Capacity, stu/hr 18.11x106 Normal (16 spent core regions at maximum 8
s.
pool water temperature of 1220F) 6 b.
Maximum (16 spent core regions plus full 42.alx10 cnre at maximum pool water camperature of 1410F)
'1%
(S System Design Pressure, pelg 200 System Design Temperature, OF 2,00h Nominal Baron Concentration, ppm SAFETY CLAS8 COMPONENT DESIGN DATA ANSI i
N18.2 Safety Design Data Class Code Components Spent Fuel Fool Cooling Pump 3
ASME III 2
Quantity / Unit Horisontal,centrifhgal Class 3 Type semialess steel Masovial 1100 Flow (each), gym 43 Head (each), ft.
do 150 Design pressure, peit 225 Design temperature, OF 20 Notor horsepower I
Spent Fuel Pool Cooling Etat Exchanger (worst case which considers 16 refuelings and one full core unloading) 3 A5ME III 4 2
Quantity /Unic Class 3 Counter flow Type Rorisontal Design heat transfer rate, stu/hr.
21.3 x 106 l
Installation 46 2
3037 Effective heat transfer area, ft
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Amendneet 48 SB142 January 19.83 FSAR TABLs 9.1-1 (Sheet 2 of 2)
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ANSI N18.1 Safety Components Desian Data Class Code Shall sida - design Design pressure, peig 150 Design temperature, OF 200 4l Primary compone.nt cooling 3000 flow rate, gym Feimary comp 6nent. cooling 85 water temperature (in), 'F Primary component cooling 99 water temperature (out), or Fouling facter, hr-ft2 - F/5tu 0.0005 Material Carbon steel Tube side - design 3
ASMk III Class 3 Design pressure, peig 150 Design temperature, OF 200 5 pent tual pool water flow 1100 rate, gym Spent fuel pool water 141 temperature (in), OF Spens fuel pool water 103 temperature (out), OF Fouling factor, hr-ft2 - F/ Btu 0.0005 c
Austenitic stainless I
Material 3
+ test Piping and valves Associated Jith Fuel Fool Cooling i
3 ASME III Material Stainless steel Design pressure, pois 150 Class 3 Design temperature, OF 200 I
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F5AR j
January 1983 TABLE 9.1_2 SPENT FUEL POOL COOLING AND CLEANUP SYSTEM MALFUNCTION ANALYSIS.
- 1 f""1U
C* ""* #'" *
"d com onant 1.
Spent Fuel Fool Rupture of a Pumps can be isolated. With only cooling Pump pump casing one of tha two pumps operating, adequate isat removal can be obtained.:
2.
Spent Fuel Pool Cooling Tube or whull Kuptura is considered unlikely.
Heat Exchanger rupture Heat exchanger can be isolated for 48 maintenance. The second heat exchangedcanprovideadequateheat removal t& der all design conditions.
3.
Spent Fuel Pool Component failure Spent fuel continues to be cooled l
48 Skimuser by fuel pool cooling ptz:ps and heat exchangers. Optical clarity of pool water may be decreased. Adequate time is available for restoration before unacceptable clarity it reached. Part of cooling flow can be diverted to cleanup 1 hop.
4.
Spent Fuel Pool Component failure Loop is isolated from fuel pool l"
Purification Loop cooling loop. Spent fuel continues to be codlad by the fuel pool cool-ing pumpd and heat exchanger. Purity of pool dater may be decreased until loopisfestored.
Adequate! time is available for restoratpn before unacceptable impurity level is reached. A bypass loop is allao provided to divert flow to the ddnineraliser if required.
5.
Spenc Fuel Pool Pipe rupture Fuel pool cannot be drained below de a level tihat provides adequate Cooling Loop shielding. Sufficient time is available for rescoration of cool-ing. Assured pool makeup water is provided by reactor makeup water sydtem or refueling water storage t!ank.
ll 1926 - NOI1915 A00d6935 AWD 208'l C8. 60'033 S10's l
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