ML20085D923
| ML20085D923 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 03/05/1965 |
| From: | Neidig R SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110170272 | |
| Download: ML20085D923 (39) | |
Text
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SAXTON NUCLEAR EXPERII' NTAL CORPORATION I
Y b
Docket V..
50-146 h
3 License DPR-4 36 CD EEE
- 2 o c'
- n.
m 5g[i o
3 age Request No. 16 u
m r!evision No. 1 N
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1.
Applicant hereby sub-dts Revision No.1 to Change Rc "2est No.16 to the e---
Saxton Techdeal Specifications as provided for in 10 CFR 50.59.
2.
To support the quested change Applicant suirdts revised pages to the Saxton Final Si.-guards Report and the SAFEGUI.RDS REPORT FOR THE SUPERCRITICAL TECH!!OILGY PR03 RAM OF SAXTON NUCLEAR E.(PERIMENTAL CORPORATION FIVF YEAR REEARCH AND DEVELO31ENT PROGRAM,, dated October 1964.
SAXTON NUCL E EXPERIMENTAL CORPORAIION By
/s/
R. Z. Neidig President (S E A L)
At st:
/s/
R. E Syr 5 ar Secretary f
Secrn and cuose:ibed to before ne t! tic
$th dr.:* of I
/s/ Charles J. Ausel O E A L) d~."'r;; Public Muhleni-rg Township, Berks County M] Occmiusion Expires October IL,1966 9110170272 010424 l
_ __l
d ebruary 1, 19o5 Docket Ho, 50-146 DYR-L y
Revision No, 1 to Technical Specifications Change Request No.16 page 1 of 5 1.
Description of Chance Make the following addition to the Saxton Technical Specifications, Supplement No. 2 to Technical Specifications incorporating changes applicable to conduct of a Supercritica' Technology Program-in the Saxton Reactor Plant.
During the conduct of tests and experiments contained in the Supercritical Technology Program, the Technical Specifications shn11 be changed to the extent indicated below, when fual is installed in the supercritical loop and the Saxton reactor is above 1 W t.
Except to the extent as changed, all of the remaintng prod slons of the Technical Specifications Mll remain in effect. Saxton s. hall advise the Commission in writing upon termination of this program.
A.
Supere-itical Fuel Assembly 1.
Uraaim dioxide (UO ) enriched to 214 i 1% shall be used for fuel, either 2
sinte red in the form of pellets, or vibration compacted ano svaged, or vibration compacted and "preusure bonded."
2.
The fuel pellets shan have dished ends initially and a void shall be-provided in the upper end plug to accommodate fission gas buildup.
3
'Ine fuel clad shall be Type 16-20 stainless steel or Incoloy, with nominal vall thickness of 10 5 mils. The clad shall rely upon the enclosed fuel for support against the coolant pressure.
L.
Seven f g r'k form the fuel assembly. The niel : oda shan have an active length of 3 ft and a diameter of 0.k50 in, S.
The fuel assemMy shall be bolted to the upper grid. The rods shan be slipped into the lover grid with sufficient cler.rance for exial expansion.
6.
The Saxton fuel ass mbly, into which the pressure tube is to be inserted, shall be located in the core position E-1.
3..
Supercritical Coolant Srster The supercritical coolant system shall consist of at least the followin6 equipment.
a'l equipment shall be fabriented of austenitic stainless steel or equivalent corroJon resistant material in accordance with the applicable ASME Boiler and Pressure Vt.ssel Code or ASA Pressure Piping Code.
-1.
Pressure Tube N
The pressure tube assembly shall consist of three compontats; the pressure tube, connector body and head adaptor flange assembly, all made of AISI Type 316 stain 1rs steel.
~
nevidlon 4.v.
1 Lv Lw-h Change Request No. 16 page 2 of 5 1
The pressure tube shall be desi6ned for kOOO poig internal pressure and zero external pressure at 675'F, and 2100 psig external pressure and zero external pressure at 675*F.
The minimum vall thickneus of the pressure tube section shall be 0 350 inches. The maximum vall thickness of the connector body section shall be 0 360 inches.
2.
Pumps s
Two electrically driven pumps shall be prcvided to supply coolant to the pressure tube. One two-speed pump is rated at 15 gym at full speed and 5000 psig discharge pressure and 7 5 gpm ai half speed at the same discharge pressure. A single speed standby pump is provided as a reserve which is rated at 5 3 gPm at the same discharge pressure. (A second two-speed pump, with the st me characteristics, may be piped in parallel v."h the afoi ementioned two-speed pu=p.)
All parts in contact with the supercritical loop tochot uhall be fabricated of Austenitic stainless stetl or equivalent corrosion resistant meterial.
3 g t Exetangers Equipment shall be supplied which vill provide specified aerating tempera-tures thrau;;hout the supercritical coolant system.
4.
Purification Equipment Equipment shall be supplied which vill maintain coolant impurity levels below those specified.
An in-line radiation monitor shall be located downstream of the condensate pump to provide an indiv ; ion of the supercritical loop coolant radiation level.
5 Accumulator An accumulator shall be provided to reduce pressure pulsations from the main coolant pumps. The accumulator shall be constructed of carbon steel lined with a protective coating.
6.
Piping and Valves All valves containing radioactive fluids, xcept instrument valves, shall be provided with leakoffs or backseats.
C.
Auxiliary Systems
/
At least the following auxiliary systems shall bc installed:
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L.$.-4 Change Request No. 16-Pase 3 of 5
4 4
1.
Shutdown Cooling Shutdown cooling capability shall be available which utilizes the high pressure and low pressure coolers with circuation provided by the condensate pu=ps.
Emergency cooling can be effected by using the e nergency condenser.
2.
Safety Injection A supply of pressurized water held in the coolant reservoir shall be discharged automatically to the accumulator connection of the loop following loss of flow, or to the pressure tube outlet line upon a loss of coolant upstream of the pressure tube, n.
Coolant Reservoir - The coolant reservoir shall have a 25-gallon capacity and be constructed of carbon steel designed for 5000 psig at 200*F.
It shall contain demineralized vater pressurized by the reservoir gas cylinder. The coolant level in this reservoir shall not fall below 15 gallons.
b.
Reservoir Gas Cylinder - The reservoir gas cylir, der shall be of all velded joint construction, carbon steel, and designed for 5000 psig.
Pressure in this cylinder shall not fall below 4000 psig.
c.
Emergency Condenser - The emergency condenser shall be fabricated
(
of austenitic stainless steel, prJvided with an overflov and vacuum I
break, and designed for 15 psig r. hell and 4400 psig at 1000*F tube side. Sufficient makeup water enall be surplied for unlimited operation.
3 Pressure Relief The supercritical loop shall be protected from overpressure by relief valves having the following nMnal settings:
a.
Outlet hne flom the pressure tube, two valves with set pressures of kC00 and 4120 psig.
b.
Discharge side of the loop pu=ps and standby pu=p, set pressure of 5000 psig c.
Discharge side of the gas compressor, set pressc e of 5000 psig, d.
Demineralized water line supplying the coolant reservoir, set pres _'e of 200 psig, e.
Component cooling water line,4et precsure of 150 psig.
f.
Diluent steam generatr line, set pressure of 60 psig.
6 Sample ion exchangers lines, act pressures of 150 psig.
A
______a
..'t-4 ChakeRequeetNo.16 Page 4 of 5 h.
_Sarplinc, Provisicn shall be ade to obtain cvpercritical loop cochnt gas and liqaid samples.
5.
Reactor Head Mozzle Cooling System A cystem shall be provided for cooling the reactor nozzle penetration used for the supercritical loop.
D.
Radioactive Waste Disposal Liquid vastes from the supercritical loop shall be directed to the Saxton Radioactive Waste Disposal Facility.
The supercritical loop gaseous vaste, after recombf nation shall be directed I
to the Saxton Radioactive Waste Disposal Facility.
E.
Elect-ical Power Standby electrical power chall be taken from the facility inverter for critical te=perature, pressure, level and flow instruments.
F.
g trumentation N
Eq.iptnent I.11 be provided to measure and record pressures, tempe m tures, una f1 ms, e, p.ints in the supercritical loop and auxiliary systems.
P G.
@ erating Limitations The following operating limitations shall apply to the supercritice1 loop operction:
Maximum supercritical fuel assembly power level 115 KWt
.hximum pressure tube inlet pressure 4000 psig Minimu= pressure tube inlet pressure 2000 psig Maximum oupercritical pressure tube outlet te=peratt.re lOOO*F Maximum 15-minute degassed gross activity of coolant 20pc/cc bhximu= chloride concentration in loop coolant 0.1 pp=
Maximum temperature of reactor vessel head flange 650*F Maximu= thimble pressure drop 600 psi Minimum loop flow
- 50) or the flow control r at point for the test being condur.1.ed 6
Revision No. 1 to bril-4 Change Request No. 16 Page 5 of 5 If any of these limits are exceeded, action vill be initiated to bring the condition back within 'lmits.
In Sup,nlement No. 1 to Technical Specifications, page 4, chanEe section 1sbeled " Change item G.3" to read:
Change 1 ten G.3 The 2enetor chall be autmatically scrammed under the followinG conditions:
Set Point Conditions Fast startup rate (maximum) 2 decades / min.
Hibh power level at startup (mximum) 25% f d.1 3cwer
~
High power level at power 20 Kdt operation (maximum) 24 M4t 23 5 W t operation (maximum) 27 M4t Lov main coolant prensure (minimum) 1600_psig 4
Lov main coolant flow above 1 M4t (r. ~.nimum) 2.2 x 10 lb/hr Lov vater level in pressurizer (:r.in;i m) 83%
Loca of main coolant pump power Contact on breakers, failure of power supply, or loss of variable frequency set clutch excitation vhen variable fre-quency set is supplying power for main coolant pump operation 3
Main coolant temperature (hot lee) (Maximum) 55h*F (23 5 M4t opemtion) f 600*F (20.0 Wt operation)
When fuel is installed in the supercritical loop and the reactor is above 1 M4t:
Condition Set point Loss of supercritical loop flov (minimum) 50% of normal flow set point, exceeding a preset-time delay Loss of supereritical loop coolant pressure (m'.ninum) 2000-psis Loss of supercrit cal loop coolant Pressure drop reversal across pressure tube 2
The scram signal conditions associated v'th the eu,.c reritical loop need be operations 1 only if a fueled pressure tube is-instr ir. the reactor.
s s
Rev3 sed Pages for' s
Saxton Final Safeguards Report and Safeguards Report for the Supercritical Technology Program
}
6 mm.
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These revised pt.ges reflect the following plant or Supercritical loop modifications as described in the Safeguards Reports.
A.
Saxton Final Safemtards Report 1.
Revised page 208.1 h
Reflects that onc of the existing plant component c, soling water punpe will be replaced with_ a pump with increated capacity to renove the heat added to the'supercritien loop by the 650 kw installed electrical heaters.
B.
Safecuards Report for the Sur;ercritical Technolorv Procram, 1.
Revised page I-1: 2 Reflects that one fuel assembly will contain only rods of incoloy
(
cladding with pelletized fuel and a second fuel assembly vill contain or.ly rods of 16-20 stainless steel cledding with vibratory compacted fuel, s
2 Revised page II-3: 6 The change in footnote number tuo shows that the supercritical fuel rated power will be attained at a reactor power level of 23.5 int, not 201Mt.
a 3
Revised page II-L: 2 s
Heat leakage has been changed to reflect change to an all stainless steel pressure tube.
4.
Revised pages II-4: 6, 7, 8, 9, and 10 lhese pages have been updated to show that the pressure tube will be all stainless cteel rather than having a transition piece and a
'ireal k/ section.
5.
Revised pages II-L: 12 end 13 Changed description of pumps to show that two pumps are required in the supercritical loop and that a third pump nay be installed but is w.s necessary.
6.
Revised page II-4:17 Indicates a change frota one filter to two filters and specifications of minimum particle nices that each filter will remove. Deletes reference to hydrogen form resins cince ammonia forn resins may also be used for chemistry control.
s
____.______m._________.
.______________m___
4 1 7.
Resised page 11-5: 2 Reflects that one of the existing plant canponent cooling water pumps will be replaced with a pump with increased capac5*
- to renove the heat added to the supercritical loop by the o30 kw installed electrical heaters.
8.
Revised page II-5:
5 Changes the set pressure of pressure relief valve PSV-2 from 4400 psig to L120 psig.
9.
Revised page II-5: 6 Changes the set pressure of PSV-5 from 150 psi
.a 200 psig.
Adat m
to the description pressure relief valves PSV-7, 8, 9, and 10.
\\
10.
Revised page II-5: 7 Deletes periodic gas samples and reference to a gas denple drier and holder.
- 11. Revised pages II-5: 9 and II-7: 4 Reflects a change in the reactor head no: le cooling systen to incorporate a flou alarm and automatic heater shutoff.
- 12. Revised page II-7: 7 i
Shows that TR-X2-10 was moved fran the safety injection line.to the enercency condenser line.
13 Revised page II-7: P Indicates a - change so that when the coolant reservoir is exhausted the level controller ad-its service water, not decineralized water.
14.
Revised-p;7- ~i-7: 10 Corrects temperature recorder identifying numbers under " Reactor Head Hotele Bleed 'lemperature".
f
- 15. Revised page II-74 E12 Deletes " Gas Sample Holder Pressure PI-X21" since gas sample system has been changed to take samples in the present sampling room.
r.
- 16. Revised page II-7: 14 Deletes second loop flow instrument FR-X4.
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3-17.
Revised page II-8: 1 Reflects a change in that amenia c.ay be used in syste:a chemist 2/
control.
18.
R3 vised Figures 11-1, II-6, and II-7 Update drawings to reflect the changes described in this Revision I to the Safeguards Report for the Supercritical Technology Program.
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203 1
! S December 19EA 203 - COMPONEIC COOLIIU SYSTEM A.
Function The function of the ec=ponent cooling system is to remove heat from the shutdown cooling heat exchanger, rain coolunt pump, non-regenerative heat exchanger and Supercritical Locp system when it it, 1; ope 2stion.
B.
Description The component cooling system is located entirely inside the containment vessel and consists of two centrifugal circulating pumps, two hect exchangers, a surge tank and the necessar/- piping, valving and instrumentation as shown on Figure 203-1.
The system is initially filled through the surge tank with demineralized water frce the secondary plant. Chemicals required for corrosion inhibition are manually added at the surge tank.
The water is continuously recirculated by the component croling pump through the equipment which requires cooling and then through the compcnent cooling heat exchanger where the absorbed heat is transferred to the river vater.
Only one pu=p and heat exchanger are required, hence the second pu:tp and heat exchanger serve as spares to insure availability of cooling vater in case of-equip-ment failure. Make-up water may be added to the system through a remotely operated surge tank fill valve.
C.
Componen+ s 1.
Corponent Cooling Heat Exchangers These heat exchangers are flanged head, horizontal, U-tube and s
shell type units. They are constructed of carbon steel with admiralty tubes.
A relief valve is provided on the shell side of the heat exchangers in accordance with code requirements. Each unit is designed for a maximum heat transfer rate of 2,055,000 Btu /hr with a tube side inlet temperature of 131*F, a tube side nutlet temperature of 100*F, and a shell side inlet tamperatu-of 80*F.
The shell sides and tube sides are designed for 150 psig end 200*F.
2.
Component Cooling Pumps Two single speed, end suction, vertically split casing, centrifugal pu=ps are provided for circulating the component cooling vater. Each pump is provided with a single mechanical seal to minimize leakage. One pa=p has a capacity of 155 gpm at a total dynamic head of 70 feet and the second has a capacity of 260 gp= at e total dynamic head of 230 feet. The design pressure is 150 psig at 200*F.
The pumps are of cast iron construction with bronze trim.
3 Co=ponent Coolira surge; ag The co=ponent cooling aarSe tank is a 3 cubic foot, cylindrical, corrosion protected cpen tank.
t i
2-1: a Revision _I e
e The first assembly will use incoloy 800 for clad material and sintered
'J02 pellets enriched to 21_',1 w/o U-235. The second ascembly will use 16 Cr 20 Ni alloy sta$nless steel cladding and vibration compacted UO2 powder of 21 + 1 w/n enrichment in U-235.
Following compaction, these rods will be swaged to raise the powder density to 93% of theoretical desnsity. _ All fuel rods in both assemblies will be autoclaved at 3000 psi und 700-750 F prior to final assembly to seat the clad firmly on-the fuel.
This operation will minimize rod diment,ional changes in reactor service and will assure a wrinkle-free clad.
The initial loop operating conditions will be set belov :aadmum design values.
During the course of the program these conditions will be t;uccessively ruised to approach the design coolant outlet-ccnditions of 10000 F at 2600 psig with clad surface temperatures approaching 1200 F 0
at PO kwt operation.
Throughout this series of tests, the loop coolant will be continuously monitored to determine gross corrosion and mass transport effects.
Each asse?.bly will be irradiated for approximately six Necks. At the end of the second irradiation period, one of the fuel assemblies will be selected for an additional six-week irradiation.
i e
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II-3: 6 Revision I 9
TABLE 11-1 TEST ASSD!BLY CIRRACTERISTICS Maximum Power Level (Das16n) 115 kvt Enrichment 21% for 80 kvt operation 3
for 115 kvt operation
[
Coolant Flow:
Design 6750 lb/hr Minime allowable at 80 kyt h500lb/hr 115 kwt 6750lb/hr I
Mars velocity thru fuel 6
^
assembly at 6750 lb/hr (nxinal)
- 2. x 10 lb/hr-ft' quantity of UO in the supercr..ical 6.151 kg 2
loop (7 rod assembly)
Quantity of UO in the 21 rods removed 12.826 kg 2
from the Saxton fuel assembly 2
Heat flux at 115 kwt: Maximum 383,000 Btu /hr-ft Average 159,000 Btu /hr-ft s
N (1) Based upon 1200*F maximum clad surface temperatures and 930*F inlet coolant temperatve.
(2) Case chosen for testing. Reactor power is assumed to be 23 5 Wt for calcu'tation of fuel power output.
(3) Assumed design limits of operation of loop.
+
To be specified after 80 kw operation.
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II-4: 2 Revision I TABLE II-2 SUPERCRITICAL LOOP COOLANT SYSTEM DESIGH DATA Pressure Tube:
Coolant temperature at outlet (max. at 115 kvt) 1000*F Design temperature 675'F Design pressure, internal LOOO psig Design pressuie, external 2100 psig Operating pressure, internal 360c psig O. D.
2 75 in.
In fuel region 24 h 3
Y Heating (maximum) 1.08 x 106 Stu/hr-ft Heat leakage thru portion of prescure tube inside of reactor
- 166,0 N Btu /hr 4
Primary and Standby Coolant Pu=po:
Design temperature 200'F Design pressure 5500 psig Design flow rate Primary pump, full speed 15 gp Standby pump, full speed 5 3 gpm Condensate Pumps:
Desi.gn te=perature 300*F Design pressure 150 psi 6 Jesign flow rate 16 gpm 5
Eeater:
e Design temperature 1030*F Temperature
.fltnd inlet (max.)
760*F Te=perature - fluid outlet (max.)
1015'F Design precsure 4000 psig 3L,000 Btu /trofthislossisduetocoolingofnozzleheadpenetration.
4
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i II-4: 6 Revision I 4.2 Pressure Tube Assembly s
The pressure tube assen.bly, shown on Figure II-6, is of the bayonet re-entry type. Coolant at 3600 psig and 6oo'F to 975*F enters the pressure tube through the lover ju:::per and flows downward through the annulus formed by the pressure tube baffles and the fuel assembly baffles. At the lower end of the pressure tube, the flow direction $s reversed to pass upward tnrough the fuel assembly and inner fuel assembly hanger baffles.
The coolant leaves through the top ju: aper at temperatures up to lOOO'F.
I A Marman Coneseal pipe joint serves to support the pressure tube assembly and prevent leakage of reactor primary coolant. This joint can be serviced by remote maintenance tools. Inlet and exit jteper piping connec-tions are made with Grayloc fittings. A remote maintenance tool is feasible for these fittings and vill be used if necessary to limit maintenance personnel exposure. The pressure tube aest.mbly consists of four components; the connector body, pressure tube extension, the head adaptor flange assembly, and the presbure tute, all cf AISI Type 316 stainless steel.
The rough machined connector bocy is velded to the head adaptor male flange.
After final machining operations, this assembly is velded to the pressure tube to form the co=pleted pressure tube assembly.
i l
Connector Body I
l The connector body is designed for k000 psig and 1000'F vith atmospheric pressure outside. A 3-inch thickness of insulation 1s-provided. The inlet and outlet nozzles are machined from eolid stock as part of the connector body. They arr: spaced approximately 16 inches apart to reduce heat transfer and thermal stresses between the two areas. A refueling port is loceted in the upper end of the connector body and is sealed with
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l
II-k: 7 Revision I a Conoseal gasket. A ring and six jack screws, made of W-5k5 steel, serve to hold the Conoceal male #1.ange in place. Each Jack screw is tightened to 95 pound feet torque to preload the Conoseal gasket with sufficient axial compression to resist any gasket covement durirq operation at k000 psi. Conoseal clanp and sleeve flange is of AISI Type 316 stainless steel.
Hydrostatie thrust due to k000 psi internal pressure and the refueling port spring is 26,500 pounds. Axial port stress in the threaded area from this thrust is 2700 psi. Ring thread shear stress is k500 psi and jack serev bearing stress and tnread shear stress are 18,400 psi and 3700 psi respec-tively. The jack screw beari g stress is equal to 1/2 of the stress required to produce 10% relaxation in 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> in W-Sk5 stainless steel at 1100*F. W-545 vas chosen for ring and jack screws because it matches the coefficient of thermal expansion of the refueling port male and female flanges, 74 addition, it possesses high strength at 1000*F; typical creep rupture strets at 100,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> at 1000*F is approximately 80,000 psi.
A is11-tone seal, just below the outlet nczzle, supports the fuel assembly nni prewrds the bypass of inlet coolant around the fuel assembly to the exit jumper. To secure a positive sealing against hydrostatic pressure, e
a refveling port spring is provided in _the top of the pressure tube assembly which 17 designed to provide a minimum sealing force of 60 lbs. The sprir4 force is based on the following assumptionn:
1)
Total thrust due to hydrostatic pressure
- 530 lbs.
2)
Weight of internal parts
.+ 75 lbs.
3)
Buoyant force 10 lbs.
k)
Baffle friction force
- 12 5 lbs.
5)
Minimum spring force at temperature
+ 650 lbs.
6)
Mi*imt=: net sealing force 60 lbs.
+
.l l
4 II h: 8 Revision I Head Adapter Flange Assembly The head adaptor flange assembly supports the pressure tube while connect-ing it to the Saxton reactor head adapter. The head adapter flange assembly screws into the Saxton reactor head adapter and is seal velded.
The assembly is velded to the connector tube. The male and female sections of the assembly are joined at the Conoseal joint and clamped together.
The assembly parts are constructed of Type 316 stainless steel.
Pressure Tube and Pressure Tube Extencion The portion of the pressure tube rasembly extending within the reactor vessel vill not be code stamped because it is completely contained within the reactor vessel which is the-ultisate container for reactor and loop ntlant. This portion, however, is designed to meet the intent of Section VIII of the ASME Pressure Vessel Code as outlined below.
Sections III-1, 2, and 3 of this report describe normal loop startup, operating, and shutdown conditions. Initially, the loop and reactor are
- brought to 2000 psi and 530*F together. Differential pressure across the pressure tubes are small during this time. The loop pressure is then increased to 3600 psi normal operating pressure followed by increasing loop temperature to test inlet-temperature.. The reactor is brought to power. Normal operating conditions hsve thus been established.
These conditions are:
3600 psi internal pressure c.nd 2000 psi external pressure for a maximum difference in pressure between the inside and outside of the pressure tube of 1600 psi;.675*F pressure tube taximum te=perature (including gamma heating) and 600*F pressure tube extension maximum temperature. Reverse procedure is fellowed during loop and' reactor shutdown.
4 II h: 9 Revision I Paragraph UG-21 of ASE Code VIII specifies the following procedure to determine minimum vessel design pressure:
"UG-21 DF. SIGN PRESSURE.
Vessels covered by thiu section of the Code shall be designed for at least the most cevere condition of coincident pressure and temperature expected in normal operation. For this condition, the maximum difference in pressure between the inside and outside of a vessel, or between any two chambers of a combination unit, shall be considered (see Paras.
UG-98andUA-60(b))."
l The most severe condition of coincident pressure and temperature expected in normal operation ja 1600 psi at 675'F in the pressure tube and 600*F in the pressure tube extension. However, for extra conservatism, the following conditions are used for design. The pressure tube extension and the pressure tube are designed to withstand h000 psig internal pressure and zero ext.rnal pressure at the above listed temperaturer and 2100 psig external pressure and zero inte.rnal pressure at the above listed temperatures.
(
The pressure tube extension vall is based on 2100 ps.g 'xternal pressure at 600 *F.
Allovable stress for SA 182 Type 316 stainless steel for these conditions is found in Section VIII of the Code to be 15,950 at 600*F. The maximum outside diameter 1-Al in. and tp minimun vall thickness is calculated from Figure UG-31 of Code VIII to be 0 360 inches.
The specified minimum vall thickness is 0 379 inches.
The pressure tube va n. thickness is based on 2100 psig external pressure at 675'F. Allowable stress for SA 182 Type 316 for these conditions is 15,875 psi at 675'F. The maximum outside diameter is 2 753 inches and the minimum vall thickness is calculated from Figure UG. 31 of ASE Code s
i II 14: 10 o
Revision I VIII to be 0 350 inches. The minimum specified vall thickness is 0 3S3 inches.
During fabrication, strict quality control and inspection procedures vill be adhered to.
All velded joints vill be fully radiographed to Code standards. All pressure containin6 mater;als vill be ultrasonically inspectet Welder and velding procedure qualifications vill be based i
on ASME Code IX.
Following fabric 9 tion, the entire pressure tube assembly vill be hydro-statically tested in accordance with Paragraph 10-99 of Code VIII. The assemoly vill be subjected to separate internal and external pressure tests.
Pressure Tube Baffles, The three 'res,sure tube baffles are fabricated from stainless steel sheet metat are provided to mininize the loss of heat to the Saxton reactor primary coc,lant and to maintain the pressure tube vall temperature at or below an acceptable value of 675'F. This is achieved by the insulating effect of three 0.020 inch thick ' layers-of stagnant vater.
The baffle design temperatures are based on 950*F inlet coolant te=perature.
The three baffles are fastened to the pressure tube baffle support cylinder at a slip joint, and the support cylinder is velded to the spring guide. The support cylinder has six slots to allow inlet flow access to the downflow channel formed by the pressure tube baffles and -
the fuel assembly hanger baffles. The lower grid-is bolted to the pressure tute baffles, s
i
- - - ^ - -
Revicion I lhe dimple interference causes the baffles to deflect radially, thus inducing a radial force on the baffles. This gives rise to a frictaen force when:
- 1) One baffle as inserted int c another.
- 2) The baffle assembly is inserted into cr pulled out frcm the pressare tube.
- 3) One baffle has an expansion relative to the cther due to a temperature differential.
It is estinated that for case (1), approximately 400 lb. force will be necessary tc overcome the frictional for e with an assumed coefficient of friction of 0.2 The maximum stress induced by the process of insertion ss 10,000 psi.
In case (2), a maxmm frictional force of 115 lb. is developed. As a result, AO lb. feree will be necessary to insart the baffle assembly and 270 lb. feree will be necded tc pull the baffles out cf.he pressure tube.
The process of renoval will induce a maximum axial ecmpressive stress of 1703 psi in the outer baffle.
For case ',3), the induced stre S ranges up to 13,000 psi.
Tne radial itcaperature grtdient oetween bafflea results in axial differential expanalen. A11owan:e is made for this by bolting all three bafflee at tne t,ettea ic the fuel assemoly and allowing them to expand freely at the top where a slip joint.15 pro-dded -to accommodate the differential cxpansicn.
All st ress levels are less than yielding and buckling strengthr.
L.3 Pu xl Two elet'.rically driven pumps shall be provided tc supply coolant to the
- pressure tube. One two-: peed pump is rated'at 15 gpm at full speed and 5000 psig discharge pressure and 7 5 gpm at half epeeo at the su e-discharge prersure. A single speed standby pump is provided as a reserve f
i 1.i. - l
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II-k: 10
- pey, Revision I 9
int erference causes the baffles to defieet. radially, t.hu' cified vall thickness is 0 353 i radial fcree on the baffles.
Tnis gives rise to a frict.
Il Jf:e is inserted 2nte another.
- l and inspection procedures vill iffle assembly is inserted into cr pulled out frca +.he pre
> fully radiographed to Code rials vill M ultrasonically
..ffle has an expansion relative to the cther due tc a temp = j qualifications vill be based ential.
mated that for case (1), approximately 400 lb. fcrea will re tube assembly vill be hydro-tc overcome the f rictional forte _.2th an assumed ne'ficie agraph 10-99 of Code VIII. The f 0.2 The r.aximum stress indu:ed by the process of in9 :
nternal and extemal pressure
- p31,
), c maximam fri:tional force of 115 lb. is developed. k it, force will be necessary to 2nsert the baffle assembt ree will be needed tc pull the baffles oui. cf the pressur<
s of renoval will induce a tiaximum axial ecepressive stre:
n the out ar baffle.
icated from stainless steel the loss of heat to the Saxton 3), the induced strees ranges-up to 13,000 psi. Tne radia the pressure tube vall temperature l
e gradient cetween taffle results in axia; differential This is-achieved by the Allowance is made for this by boltang all three baffles
,1ck layers of stagnant vater, he fuel asseno]y and-allowing them to expand. freely at t!
on 9e 7 iniet coolant provided to accoraaodate the nifferential cxpar Lp joint.fs d evels are 1ces than yie' ding and cuckling-S trengths,
' essure tube baffle support t cylinder is velded to the i
six slots to allow inlet flow the pressure tube' baffles and
.cally driver.
-.aps anall De provided tc supply coolant to tb e. One two-speed pump is rated at 15 gpm at full speed iower grid fr-oelted to the pressure lischarge pressure and 7.5 gp: at half epeea at the same ir essure.
A single speed standby pump is provided as a re-I
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T! e a nplc interference causes the baffles to defleet-radially, inus inducir.g a radial force on the baffles.
This gives rise to a friction forer when:
1)
One baffle a s insert ed int e another.
2)
The baffle assembly is inserted into cr pulled out frc= the pressare tube.
I
- 3) One baf fle has an expansion relative to the cther due to a temperatur e differ ential.
It is estimate.d _that for case (1), approximately 400 lb. f orca will be necessary to overccme the f rictional forSe with an assumed coef ficient of fricticn of 0.2 Tne maxinwn stress induced by the process of insertic-n as 10,000 psi.
In case (2), a maxaram frictional force sf 115 lb. is developed. As a result, LO lb. force will be necessary to insert the baffle assemL:y and 270 lb fcree wall be needed tc pull the baffles out cf the pressure tube.
The process of renoval will induce a raaximum axial ecmpressive stress cf 1700 pai in the outer baffle.
r For case ',3), the induced stress ranges up to 13,000 psi. Tne radial t saperature grad;e it netweer baffiea results in axial diff erential expansion. Allowan:e is reude for this by bolt 2ng all three baffles at tne cettca to the fuel assenbly and allowinc thei tc cxpand freely _ at_ the _ top where a elip -jcint-is provided to ac.cnanocate the differential expari.cn.
All stress levein are less than yltiding and buckilt.g itrength:.
L.3
_ P_unp; Two electrically driven pumps shall be provided,1c supply coclant to _ the isreasure tube. One two-speed pump is rated at 15 gpm av. full speed and 4
5000 psig discharge pressure art. 7.5 gpm at half epeea at the same di?:harge pressure. A -single speed standby pump is previded as a reserve
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wni:h 1: rated at 5.3 gpm at the sane disenarge pressare.
(A eecord two-epeen pump, with the same characteristics, may be piped in parallel with the aforementioned two-speed pump. )
The standty pump 1s energized by the loop ficw comroller or manually f.cm the plant contrcl room.
Electric pcwer for the loop pump is provided from the supercritical loop 440 V bue. Electric power for the standby pump comes from the moter control ce.ter of the Saxten reactor electri:al system.
Each pamp is a triplex positive-displacment type, with integral check valves. All parts in contact with the coolant are fabricated of austenitic stainless steel or equivalent eerrosion-ree$stant mater $al.
A leakeff is prcvidea on the pump packing gland to ec11ect coolant before it can lean to the reactor centainment atmosphere. The coolant leakage is piped inroust. a strainer to pump suction for return to the loop.
The pump shaf t is made long enough te prevent the oil-wetted portion from contact-ing the pump paccng.
i L.a Heat Erbanners Fea t e:
Tne heater ratses tne coolant temperature to the required pressure tube inlet conditions and provides control-to maintain this temperature-constant.
The total heater capacity-is 650 kw.. The u.it consiste of forty-two ir.dividual heater sections arranged in three' identical parallel patns, e
Each section_ consists of a straight run of pipe containinE a single m
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l 11-4: 17 t
Revision I Denincraliz$r A f1'ishstble, mixed-bed dcmineralizer renovos ionic impurities and corrosion products from the 1 cop coolant stream. A retention screen on both sides of the resin bed prevents the loss of resin particles to the outlet line.
The resin can be removed through a resin flush line abe e the retention screen. A screen at the inlet nozzle prevents resin f"x1 entering this line during backflush operations. The vessel is refil. ed with fresh resin through a fill line which can also be used for ti e insertion of resin sample probes.
The demineralizer vessel and internals are made of austenitic stainless steal with all joints and connections welded.
Local radiation shielding is provided for the demineralizer. The supercritical loop domineralizer is located near the reactor plant domineralizers to permit use of the existing resin handling lines r.ad equipment. The valve located.behind the shielding has an extensj on handle to pem.it operation during resin sampling or replacement.
Filters Tuo cartridge-type filters are provided to remove resin fines which may have passed througn the domineralizer retention screen. One. filter is sized to rencve 5 micron or larger particler and the other is sized tc remove 25 nicron or larger particles. The filter cartridge may be removed from the filter container and replaced if it becomes fouled. The filter l
container is constructed of Type 304 or 316 austenitic stainless steel.
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11-5: 2 Bevision I--
Cooling vater flows to the vacuum pump seal vater cooler and recombiner condenser in series. The component cooling vater pressure relief valve, PSV-6, is set to relieve at 150 psig. In order to assure an adequate supply of component cooling vater to both the Saxton System and the Super-critical Loop, one of the 155 gpm component cooling pumps is to be replaced by a pump of the same type with the same design parameters but with a 260 cpm capacity.
5,2 Shutdown Cooling Shutdown coolin6 utslizes the high pressure and low pressure coolers described in Section II-4, Supercritical coolant System. The circulation is supplied by the condensate pumps. In addition, emergency' cooling can be effected by using the emergency condenser described in Section II-5.4, 1
Safety Injection System.
53 Coolant Makeup The cupercritical loop is filled by gravity with vnter supplied from the head tank. The water enters the loop piping at the suction of the super-critical coolant pumps. During filling, the standby loop pump is operated to :1rculate water through the. loop. The vent line from the p1 essure tube outlet to the collection header is open to instrument LI-X4 for level indication.
The head tank provides NPSH for the loop pumps during cperation of the supercritical loop. The tank is a vertical cylindrical vessel inbricated of stainless steel and is provided with an overflow..It'is designed for r
a pressure of 65 psig or full vacuum at 312*F.
54 Safety Injection The Safety Injection System contains the following equipment:-
a)
Coolant reservoir b)
_Eer.ervoir gas cylinder n
i 1
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t-11-5: 5 Revision I S.5 Pressure Relief l
General Description The supercritical loop is protected from overpressure by relief valves on:
a) outlet-line from the pressure tube, b) discharge side of the 100p pump and standby pump, c) discharge side of the gas compressor, d) demineralized water line supplying the coolant reservoir, and e) component cooling vater line.
Two rupture discs are also supplied. One protects the low precsure cooler from overpressure in the inlet. A recond protects the deaerator from overpressure. An automatic valve is located between the pressure tube inles and outlet lines to protect the intercnanger in the event of blockage of the pressure tube. Upon receiving an excessive positive pressure drop signal, the valve automatically opens to permit the flow to bypass the pressure tube. This bypass is also used to flush out the
(
pressure tube connectors before they tre opened.
l L
1 Pressure Relief Valves The pressure relief valves are self-actuated, totally enclosed, spring-loaded valves.
The valves on the outlet line from the pressure tube, PSV-1 and PSV-2, diccharge to the storage well below normal water level. Each valve is designed to relieve one-half of the maximum combined flov of the loop pump and the standby-pump. The set pressures are 4000 and 4120 psig respectively.
The valve on the discharge side of the loop pump, PSV-3, relieves to the suction side of the pump. The set pressure.1s 5000 psig..
{
II-5: 6 i
F.evision I l.
l l
The valve on the discharge side of the gas compressor, PSV-4, relieves to the at*.a 'phere. This valve is desi6ned to pass 20 times the nominal-discharge rate from the gas compresaor at a set pressure of 5000 psig.
l The valve on the demineralized water line, PSV-3, discharges to the -
atmosphere. The set pressure is 200 psig.
For PSV-6, see paragraph II-51.
The valve on the diluent steam generator line, PSV-7, relieves to the discharge tank. The set pressure is 60 psig.
l The three valves on the three sample system ion exchange columns, PSV-8, 9, and 10, relieve to the collection header. Their set pressure is 150 psig.
l l
Ruoture Discs The rupture disc on the inlet line to the low pressure cooler relieves to the line from the deaerator to the discharge tank.
It is set to relieve at 1000 psig. The rupture disc fro;a the deaerator relieves to the discharge tank and is set to relieve at 50 psig.
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II-5: 7 Revision I 56 Sampling General Description The Sampling System is shown on Figure II-7 Two types of samples are taken from the supercritical loop:
a) continuous crud samples b) periodic liquid samples Crud samples can be taken continuously frcm three points in the loop; immediately upstream of corrosion specimen holders 1 and 2 and down-stream of corrosion specimen holder 3.
Each sample stream flows throu6h a sample cooler, then through a pressure-reducing valve into a mixed-bed sample ion exchanger. Impurities in the stream are retained in the ion-exchange resin. The sample Etream is returned to the loop at the deserator.
Periodic liquid samples are also taken upstream and downstream of the demineralizers and upstream of the low pressure cooler. Since these i
are cold, low pressure streams, they are routed to the plant sampling I
system, outside the vapor container, vnere normal sampling techniques l
may be used.
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Sample Coolers l
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Three sample coolers are provided to reduce the sample stream temperature sufficiently to permit letdown without finsting. Each cocler is a. double-pipe coil unit. The inner tube, which contains the sa=ple' stream, is made l
II-5: 9 Revicion I be cooled. This function is accomplished by bleeding 500 lb/hr of I
reactor coolant th2ough the annulus between the pressure tube and the penetration nozzle. The bleed stream flows throuEh a cooling coil which is ireersed in the water in the storage vell and then passes through a pressure reducin8 valve to the Saxton reactor purification system dovn-stream of the pressure letdown valve. Bleed flow rate is indicated on the loop control board and an alarm is activated by flow belov 50% of the set point. A heater shut-off signal is generated at no flow conditions.
In addition, an alarm is activated on high nos.zle temperature.
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II-7: A Revision 1 During a total loss-of-flow accident (defined ac reduct3 cn it flov te below 50% of set point) the instrument receives and transmits the sa:ne signals ac during a partial loss-of-flow with the fo11owia6 additiccs:
1.
An output signal to scrum the reactor and activate an alarm on the reactor scram panel. If the flow is brought above the 50% limit before a preset delay time elapses, the scram signal is blocked.
2.
An output sigual to the coolant reservoir isointion valve operator to open the valve.
3 An output signal to the loop pressure control valve, PRO-X6V, which suppresses its nomal control function. Operation of the pressure control valve is then assumed by the flow controller, which maintains a preset constant flow. The loop pump bypass "alve is closed and receives no control signal during this opersticu. The flow controller is reset manually.
Sample Flow, FRC-X15, FRC-I16, FRC-Il7 Flow recortier-controllers in each sample path regulate the letdown valve to maintain a constant sample flow..The f] ~4 is recorded on the loop control board. The records c.re used in =1Hng quantitative studies of crud level in the sample streams.
l l
Reactor Head Nozzle Bleed Flow, FIC-I9 l
A flow controller on the bleed line from the reactor reguhtes a control l
valve to maintain a constant cooling flow through the reactor head nozzle which supports the pressure tube. The flow rate is indicated on the control board with an alarm activated when the flow is reduced to 50%
of the set point. A heat shutoff signal is also generated at no flow conditions.
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II-7: 7 Revision I Emergency Condenser Line Temperature, TR-X2-10 A temperature detector is located on the emergency condenser line connected to the pressure tube outlet piping. This teigerature is recorded by the multi-point recorder on the loop control board. This detector monitors emergency condenser inlet temperature when this item is in operation.
Safety Injection Flow, FIC-x3 An indicator-controller on the safety injection line regulates a control valve to maintain a constant injection rate. The controller is normally inoperative and must be activated by a loss-of-coolant signal fram the pressure tube differential pressure controller, PRC-X4. Once activated, the injection flow controller continues in operation until manually shut off. The injection flow rate into the pressure tube is indicated on the loop control board.
l l
The following scram signals are provided by the supercritical loop instrumentation:
Instrument Reason _
PRC-X6 Loss of coolant PRC-Xh Loss of coolant l
FRC-X1 Loss of flow The lines for these three scram signals are connected -in parallel into the Saxton reactor scram circuitry and in no vay affect the functioning of any of the other Saxton reactor scram signals. These scram signal connections need to be operational only if a fueled pressure tube is installed in the reactor.
-_., _ _ ~ _.. _.. _.... _. _
Ja-i: 0 Revision I Coclant Reservoir Level, LIC-X6, IA-X7 A level-indicator controller positions a three-way valve to admit service water instead of coolant reservoir water to the loop when the coolant reservoir is exhausted.- The valve sLmultaneously closes off the reservoir to prevent injection cf the pressurizing gas into the loop.
An alarm on the loop control board is actuated by a low-level signal.
The reservoir level is cor.tinuously indicated on the loop control board to provide additional not2ce of leakage frcm the vessel.
Enerrenev Condenser Ievel. IL-X2 A level controller on the emergency condenser operates a makeup valve to replace vaporization losses and keep the condenser coil submerged at all tLnes.
7.5 Process Instnmentatien I
a) Temperature i
Int erchancer Temperatures TR-X1-13,14,15, X2-4 Temperature detectors are located on the four lines entering and leaving the interchanger. These temperatures are recorded by a I
nultipoint recorder on the loop control board.
The recorded temper-l atures permit evaluation of interchanEer performance.
l l
Pressure Tube Inlet Temnerature. TR-X3 l
l The temperature. of the coolant entering the pressure tube is recorded on the locp control board, This temperature is used as a check on the pressure tube inlet temperature control and for estimating.
pressure tube heat losses.
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II-71 10 Revision I I.ow Pressure Cppler Outlet Temperature, TRC-X18 A temperature recorder-controller on the om et of the low pressure cooler controls component cooling water flow to the cooler to main-tain a constant outlet te:::perature. The temperatura is recorded on the loop control boerd.
Safety Valve Discharge Teeperature, TR-X2-8, 9 Te=pe mture detectors are located on the discharge lines of pressure safety valves, PSV-1 and PSV-2, to indicate leakage through the valves or the lifting of the valves. These temperatures are recordc<1 by a cultipoint recorder on the control board.
Reactor Head Nozzle Bleed Temperature, TR-X2-12, X1-16 l
Temperature detectors are located at the inlet and the outlet of the cooling coil which cools the bleed from the reactor. TR-X1-16 gives an indication of the effectiveness of the system in cooling the nortle.
TR-X2-12 gives an indication of a temperature which would cause flashir, across the pressure letdown valve. The temperatures are recorded by a multipoint recorder on the control board.
Vacuum Pu=p Seal Water Temperature, TR-X2-13,14; TC-X21 TR-X2-14 is located on the seal vater reservoir. TR-X2-13 is located on the seal water line to the vacuum pump, and permits detection of excessively high seal vater terperature.
These temperatures are recorded by a multipoint recorder on the loop control board. TC-X21 is a locally _
mounted temperature controller on the seal vater line to the vacuum pump and controls the component cocling water supply to the vacuum pump seal vater cooler and tha recombiner condenser.
II-7: 12 Revision I Loop Pump Discharge Pressure, PR-X20 A pressure detector on the loop pump disebrge piping sends a nignal to a recorder on the loop control board. This reading and the accumulator pressu3e reading PR-X2 are recorded on the same chart.
A comparison of the tvo traces gives an indication of the accumulator pulsation-damping effectiveLesa.
Gar Reader _ Pressure, PI-X11 A local pressure detector on the gas header monitors gas pressure during coolant reservoir filling operations and provides a check on the compressor control, PC-X10, during tests.
Deaerator Pressure, PRO-X22, PA-X8 A pressure recorder-controller on the d.eaerator prevents excessive pressure on the vr.cuum pump by closing the pump inlet valve if deaerator pressure exceeds a preset value. An alarm on the loop control board.
is actuated by a high pressure signal. The deaerator pressure is continuously recorded on the-loop control board.
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II-7: 1h l
Revision I c)
Flow Demineralized Water Flow, FR-x3 A flow detector is located in the demineralized vater line to the head tank and the emergency cendenser. The flow is recorded on the contiol board and informs the operator of the frequency of head tank filling, water makeup requirements of the loop, leakage of water into the emergency condenser, and emergency condenser cooling vater require-mente durin6 operation.
Loop Pump and Standby Pump, Gland Leakoff Flov, FI-X10 A flow detector is located in the gland leakoff lines of the loop pump and standby pump to measure leakage through the pu.4 packing.
The reading is indicated on the control board.
d)
Level Head Tank Level, LIC-X1 A level indicator-controller operates a makeup valve to_ maintain the water inventory in the hea'd tank above a preset level. The instru-ment provides a continuous, level indication on the. loop control board.
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