ML20085D583
| ML20085D583 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 02/29/1964 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110160283 | |
| Download: ML20085D583 (31) | |
Text
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APPENDIXJ TECilNICAL SPECIFICATIONS 10 OPERATING LICENSE NO. DPR-4 SAXTON NllCLEAR EXPERiflINTALf0RPORATION FEBdih64 DATE:
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.t SaXEON N'JCLEAR hXt$3DINTAL CORPORATIOm TECHNICAL SPECIFICATIONS A.
SITE The facility shall be located within the Saxton Steam Gen 3 rating Station Company near the Borough of Saxton, property of the Pennsylvania Electr11 The Pennsylvania Pennsylvania, in Liberty Township, Bedford County, Pennsylv ll be 800 Haystown Branch of the Juniata hiver.
the containmenc vessel to the nearess boundary including the riv l
i Company generation and transmission of electric power by the Pennsylv feet.
t nd of the proper'.y.
B.
CUSTAINMENT The contcinnent vessel shall be a vertical cylindrical steel vessel with a
- Design, hemispherical head at the top and an elliptical head at the bottom All pressure hoiler and Pressure Vessel Code, as modified by Code Case 1272N.d B parts of the vessel shall be fabricated of ASTM Specification a-201 Gra eP Firebox quality steel.
tions, and forgings snall be neat treated to ASTM A-350 specificatinns.
Tne following design pressures and nominal dimensions shall apply 109 ft. 6 in.
Over-all height 50 ft.
Diameter 50 ft. L in.
Depth below grade Thickness of concrete 1 ft. 6 in.
liner below grade lhl,500 cu.ft.
Met free volume 30 psig Design internal pressure 0 5 psig Design external pressure The containment vessel penetrations shall be as follows:
1.
Electrical Sealed by pressure Mineral insulated with a metallic sheath.
gland seal threaded into a coupling on the outside of the a.
cu..tcinnnnt vessel, and a second pressure gland seal on the ir. side. - Provision maoe iv4 tc;tir.g.
Sealed by Silicone rubber insulated with a lead sheath.
filling part of crupling and nipple assembly at penetration b.
with a sealing compound and by pumping silicone compounds into cable.
Provision made for testing.
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s.
2.
Coaxial and triaxial instruntntation cables with polyethylene c.
insulation and a vinyl or equivalent jacket. Scaled by a pressure sealed receptacle on the outside of the containment vessel and sealing bushing on the inside.
Itovision made for testing.
d.
Plastic insulated strain gage leads and var-glass insulated thermocouple Icads.
Senled by passing throuCh a "Cor.ax" or equivalent bare wire thermocouple gland with sealant plug.
Provision made for testing.
2.
Mechanical Fenetrations for lines which operate below 2500F. A section of a.
pipe welded to the containment vessel plate and shop stress relieved.
b.
Penetrations for 3-inch safety injection lines and lines which operate above 2500F. Thermal sleeves scaled to the pipe system ry an expansion joint or solid metal end connection.
c.
Ventilation penetratione. A section of pipe welded to the containment vessel plate and shop stress relieved.
d.
Vacuum breaker penetrations. A section of pipe welded to the containment vessel plate and shop stress relieved.
l 3.
Access a.
Equipment access.
A flanged bolted opening six feet in diameter.
l Internal pressure helps effect a leak-proof seal. This access may be opened under conditions specified in Section N.5.h.
b.
Personnel entrance.
Two double door air locks mechanically interlocked to prevent both doors from being opened simul-l taneously. Tnis interlock mechanism may be defeated ander the conditions specified in Soction N.S.h.
Personnel will not be allowed to enter the containment vessel '
c.
when the reactor is critical or reactor startup has been initiated.
1 h.
Installation of additional electracal and mechanical penetrations shall be permitted, provided that they are of the same design authorized in these specifications, and that each penetration so installed under-goes a leak test.
Penetrations'which are repaired or modified shell be subjected to a leak test.
5.
During reactor operation the containment internal pressure shall be maintained at less than 5 pai. A containment vessel hign pressure alarm shall be provided in the control room, Valves in the main steam line, ventilation purge lines, and purificatior. system lines shall be actuated remotely from the control room.
Power operated valves in the lines between the storage well in the containment vessel and the refueling water storage tank shall close automatically upon high containment vessel internal pressure.
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C.
MAIN CJJLANT SYSTEM Tne main coolant system shall consist of one piping loop, one reactor vessel, one canned motor pump, and one steam generator.
All equipment except the reactor vessel shal] be fabricated in accordance with the applicable ASME Boiler and Pressure Vessel Code or ASA Pressure Piping Code.
The principal features of the major conponents shall be as follows:
1.
Reactor Vessel Tne reactor vessel shall be a right circular cylindrical container with a hemispherical bottom head and a flanced and gaskettd removable top head.
The top head shall have provision for a monitered leak-off :7nnection and seal welding.
The vosoci is designed for a working pressure of 1500 psia and constructed of carbon steel -
A.O. Smith 11350 Grade "A' Special and internally clad with 316 stainless steel.
The vessel shall have the following nominal dimensions:
Inside diameter 58 inches.
Dver-all height 216 inches Top head thickness 5jinchen Bottom head thickness hg inches Cylindrical shell thickness 5 incht:0 The main cylindrical shell shall be fabricated by a multilayer construction technique. The main coolant irdet and outlet shall be via 12-inch nozzles situated above the level of the active core.
Six control rod mechanism thimbles shall be threaded and seal welded to the bottom head. The top head shall have eleven openings for insertion of test elements, instrument leads, and a superheat loop.
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2.
Steam Ocnerator l
The steam generator shall be a vertical shell and U-tube type with integral steam drum and three stages of moisture separation. The steam generator shall be designed for operation at 28 M4t.
All l
surfaces in contact vith the nain coolant water shall be either l
stainless steel or Inconel.
Tube material will be 30h stainless steel and shell material will be ASTM A-212 Grade B carbon steel.
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The vessel shall have the following nominal characteristics:
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Shell side design pressure 1800 psia Steam generation rate at 28 MWt 97,000 lb/hr l
l 3.
Main Coolant Pump The main coolant pump shall be a single-stage centrifugal unit of the canned motor type with a design pressure of 2$00 ps1.
nil metallic surfaces in contact with the main coolant shall oc fabricated of stainless steel or Inconel.
Tne flow in tne nain coolant loop may be controlled by varying the frequency of the pump electrical supply.
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Main Coolant Pipe and Fittings The material of all piping in contact ith the main coolant shall a
The lines connecting the reactor vessel to be stainless steel.
che steam generator and the main coolant pump shall be nominal The line connecting the 12-inch Type 316 stainless steel pipe.
steam generator to the nain coolant pump shall be nomit.k1 lb-inch Type 316 stainless steel pipe.
Elevation of the steam generator and main coolant pump shall be above the level of the reactor nozt'es.
An audible and visible alarm in the control room shall occur when 3.
the following operating limitations are reached.
a.
Minimum inlet pressure b.
Minimum flow rate Maximum mixed core exit temperature c.
D.
NUCLEAR PLANT AUXILIARY SYSTEMS All components of
- he nuclear plant auxiliary syt.kms Jhall be fabricated in accordance with the applicable ASME Boiler and Pressure Vessel Code or ASA Pressure Pipsng Code except where special code cases apply, 1.
Pressurizer Vertical cylindrical vessel with Type pressure maintained by electric immersion heaters and spray system.
Heaters protected with low liquid level heater shut-off.
Containment vessel Location 2500 psin Design pressure 6680F Design temperature 9h.$ cu.ft.
Free volume ASTM Grade B carbon stoel internally Material clad with stainless steel Normal liquid volume 20 cu.ft.to 80 cu.ft.
Relief valve discharge point Discharge tank 2.
?urification System a.
Major components Regenerative heat exchanger Material Type 30h stainless steel Design pressure 2750 psig j
Design capacity h,500,000 Btu /nr.
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5.
Non-regenerative heat exchanger f
Material - tube side Type 30h stainless steel Design pressure 150 psig Design temperature 3000F Design capacity 1,800,000 Btu /hr.
Demineralizers (2)
Material Type 30h stainless steel Resin capacity 6 cu.ft.
Design pressure 150 psig Design temperature 3660F Sarge tank Material Type 30h stainless steel Design pressure 150 psig Design temperature 366 F Desi n capacity 75 cu.ft.
C b.
Capacity The purification system shall be designed for a flow rate of 30 gpm.
3.
Charging System A charging system consisting of two motor-driven horizontal, triplex, reciprocating pumps, each having an adjustable capacity of 1 to 15 gpm at a total dynamic head of 2500 psig, shall be provided to charge degasified, demineralized make-t.p water, concentrated borated water, and water from the purificatien system into the main coolant system.
These pumps shall be in operable condition during operation of the reactor above 1 MWt, except that one pump may be rendered inoperable for the purpose of minor maintenance such as repacking the three piston packing glands one at a time, so that the pump can be placed One or back in service within a period of four hours, if necessary.
both of these pumps shall operate intermittently as required for the purification system, and for volume control of the main coolant system.
i h.
Sampling System Provision shall be made to sample the main coolant on the discharge side of the main coolant pump, pressurizer water, and inlet and outlet of the purification and boric acid demineralizers, i
S.
Shutdown Cooling System A shutdown cooling system shall be provided for removing decay heat after the main coolent system pressure has been reduced to 150 psis or less. This system shall consist of a heat exchanger and two centrifugal pumps. An audible and visible alarm is provided in the control room if flow drops below 30 gpm when this system is in operation, e
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6.
E.
SECONDARY COOLANT SYSTEM The secondary coolant shall be light water and stean.
Major equipment in the secondary system shall consist of Unit No. 2 turbine A pressure generator, Unit No. 2 surface condenser, and associated piping.
reducing station shall be provided to throcile the stean generator outlet pressure All components shall be fabricated in accordance with to turbine inlet pressure.
the applicable ASME Boiler and Pressure Vessel Code or the ASA Pressure Piping
- ode.
F.
REACTOR CORE The reactor core having the following features shall be provided:
The nain coolant shall be light water, and shall serve as the moderator 1.
The designed effective reflector thickness shr.11 be and reflector.
lo inches.
Uranium dioxide (UD2) initially enriched to nominal 5 7% U-235 snall be 2.
used for fuel.
3 The fuel assenblies shall be nupplied as follows:-
a.
General description Each nain fuel assenbly shall have a total over-all length of 50.25 inches with a nominal fuel length of 36.6 inches and shall approximate a 5 386-inch square in cross section.
The fuel rodo shall be composed of stainless steel tuben which contain uranium dioxide fuel in the form of cylindrical ceramic pellets.
The rods shall be arranged in a square lattice with an initial 0.580-inch center-to-center distance.
The pellets shall have the following initial dLmension:
Diameter 0.357 ! 0.0005 inches Length 0.732 1 0.050 inches The end of asch pellet shall initially be dished. The total pellet column tolerance shall be 0.366 inches initially. The initial clad inside diameter shall be 0.361 1 0.0005 inches. Tne diametral clearance between clad I.D. and pellet 0.D. shall ~oe intially 0.00L 1 0.001 inches.
Tne gap between pellet stack and internal plug end shall cont,ain sinterec aluminum oxide ( Al 0 ) circular hollew discs, to prov$ de 23 a 0.17L to 0 352-inch end gap initially. The initial moisture content of the pellet stack shall not exceed 75 ppm on a weight The fuel rod ends shall be itaitially hermatically sealed basis.
with end plugs welded to the tubing.
Those fuel rods which require no further veldin.; shall be clad with 0.015-inch wall of T7Pe 304 weldec stainless steel 10% cold-worked with a h00 ppm maximum cobalt content. Tne end plugs shall be Type 304L stainless steel.
Those
.a 7.
fuel rods which require 'sub8equent brazing shall be composed of 0.028-inch will of Type 31.8 rian fGd carn.T4'ai5ttded etninlessThe end plugs sh steel with a 500* ppm maximum cobalt.centent.
Type 30h or 3OhL stainless steel.
b.
Main fuel assemblies Group 1 shall be a 72-rod assembly arranged in a 9x9 lattice with The nine fuel rods in the outside rows removed from one corner.
adjacent recesses of two fuel assemblies, when positioned in the core shall form an offset cruciform slot for the control rods.
Group 2 shall be similar to Oroup 1 except that the center 3x3 fuel rod cluster shall constitute a removable subasaembly.
Provision is also made for two removable rods in each assembly.
These positions will be filled during operation to prevent water slot flux peaking.
The main fuel assembly cans shall consist of perforated 0.028-inch stainless steel enclosures ei.h with four spacer grids placed The spacer grids shall be welded to the on ten-inch centers.
enclosure in parallel planes perpendicular to the length of the The grids shall be fonned by brazing straps which inter-assembly.
The straps shall provide lock in the manner of an egg crate.
The fuel rods shall fingers which are bent to form spring clips.
be free to expand axially without restraint.
Nozzles at both ends of the assembly shall position the assemblies The nozzles of the active assembliet in the core support plates.
The nozzles of shall serve as coolant inlet and discharge ports.
the dammy assemblies shall be designed +.o restrict the flow through The top nozzles shall be machined to provide engage-the assembly.
ment surfaces for the handling tool.
l The end plates of the nozzles shall retain the fuel rods within the The end plates shall be perforated with holes located and l
sized so as to produce the necessary pressure drop and flow distri-can.
i bution of the coolant, Special 3x3 removable subassemblies t
c.
The center 3x3 removable subassemblics shall be similar in const i
enclosure is 0.020-inch to the main fuel assemblies except that the perforated stainless steel and the fuel rods shall be spaced on an initial 0.535-inch pitch.
Special L-shaped subassemblies d.
Tne L-shaped subassenblies shall be composed of nine fuel rodsThe pi spaced on an initial 0.500-inch pitch.
along the length of the assembly by five parallel rows of formed tubular ferrules brazed to adjacenc fuel rods.
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CONThcL A!C SAFETY SYSTDM 0.
1.
Control Rods General deceriptiop a.
The cross-sectional shape of the control rods shall be an offset It shall be composed of two senemblics, an absorber or top assembly and a fuel follower or bottom assembly cruciform.
joint and a fixed center alignment pin.
b.
Absorber assembly The absorber, or top assembly, shall be composed of three main pieces riveted together as followst The topmost section is the stainless steel leader, part of which The projection is always projects above the upper core plate.
machined as an inverted cutaway "T" which provides engagement surfaces for the same handling tool used on the fuel assemblies.
The center portion is the silver-indium-cadmium alloy Both sides of in the core when the control rod is fully inserted.
the blades near their outside edges are machine grooved along the length to accept 9/16-inch wide by 1/16-inch thick stainless steel rubbing straps which serve se the rubbing barfaces on the guideThe absorbe blocks mounted on the core support plates.
It is sub-is nickel-plated to an initial 0.5 mil thickness.
sequently heat treated to diffusion bond the plating to the base alloy, to anneal the Ag-In-Cd for maximum creep strength, and to stress relieve the materials.
The bottem portion of the absorber assembly is an inverted stainless steel "T" witn a countersunk nole on the center line to form the male portion of the joint between the abscrber assembly and the fuel follower assembly, Fuel follower assembly c.
or bottom assembly, shall be fabricated of three The fuel fo'.Ar main sections
- 4. follows:
The top cf tnis assembly is a type 30h stainless steel cutaway fit'for the bottom absorber inverted "T" which provides a clost A conical pin is welded on the center line of the cutout end.
to mate closely with its counterpart's countersunk hole.
These are The center pertion nas 1B fuel bearing follower rods.
nase in three compartment sections with stainless steel plugs welded to the 0.022-inch thick wall cladding at intervals of apprcximately 12-1/6 inches.
Each compartment separator plug has Orooves on the outside a snall hole crilled through its langth.
of the separstor plugs are machined to accept cruciform-s on ar. initial 3.5?S-inch pitch and fusion or resistance welded to straps.
the tie strap.
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9.
The bottom is an offset cruciform 17pe 30h stainless steel sectic n with a center line hole bored up from the bottom to accept the The control rod plug of the control rod drive shaft connection.is firmly connected to the d the last nine inches of scram travel.
In the fully scranned position, the control red is unlatched from the drive shaf t and can be removed.
2.
Control Rod Drive Mechanism General description a.
The control rod drives shall be friction grip magnetic jack-type Magnetic fields established by operati.ng coils outside mechar. isms.
the pressure housing shall exert holding or moving forces on the pole pieces and drive rod bundle inside the housing.
b.
trive mechanisn design paraneters 60 Normal length of travel, in.
b2 Maxinum length of travel, in.
2500 Design pressure, psic 650 I+ sign t emperature. OF Nornal load attached to drive shaf t, lbs.
125 Maximum load on drive shaf t, lbs.
250 Approxinate incremt.nt of movement, in.
1/32 4
125 1 10%
Operating coil voltage, d-c Position indicating coil voltage for 230 reactor operation,60-cycle a-c A 100-cycle power supply for position indication may be used for additional accuracy needed in experimental work, bet this supply is not necessary for reactor operation.
Tne reactor shall be automatically scrammed under the f(llowing conditionst 3.
Set Point Conditions (Maximum) 2 decades /cin.
Fast startap rate (Maximum) 5 MW High power level at startup (Maximum) 2h Md High power level at power (Minimum) 1600 psig Icw main coolant pressure Low main coolant flow (above 1 MWt)
(Minimum) 2.2 x 1@ lb/hr Low water level in pressurizer (Minimum) 8.3%
Contact on breakers, Iris of main coolant pump power f ailure of power supply, or loss of variable frequency set clutch excitation when variable frequency set is supply-ing power for main coolant pump operation 6000F High main coolant temperature (hot leg) (Maximum) l
L.
The follovf.ng inter 1 Den. shall be provided:
IZE!
Autenatic during all Limit the maximum reactivgty Electrical insertion rate to 2 5x10- /see operations (Adjustable resistors)
Lim!
,d withdrawal to Adjusted periodically Dectrical e 2% shutdown margin based on rod worth (Relay on }.osition prc curves and operating indicator coils) with one stuck rod conditions Automatic during Remove startup rate rod Electrical stop and scram above 10%
startup power Prevent automatic operation Automatic durinf.
Electrical of control rodo below 10%
startup and drops in power power Tne following by-passes or over-rides shall be provided:
5.
Condition of Use Method By-pass.
Power operation Source range channels Manual switch in main 2 nv on control room above 7.$x10 intermediate range Below 10% power and Power range channel Manual switch in main when any power range coincidence control room channel is not operating
- Startup power level Manual switch in main When power level exceeds 10%
control room scram Low main coolant or Push button in nain During startup or control room (self-reset cooldown pressurizer pressure above 1885 psic)
During startup, cool-Safety injection Manual switch in main dovn, cold shutdown control room or testing of saft.ty injection pumps Startup instrumentation shall consist of source range and intermediate 6.
channels.
Source range channels shall cover five decades starting no higher than
'/.5 x 10-2 nv wnile ingermediate range channels chall cover from 2 5 x 102 nv to 7 x 10 nv which is up to 10% full power, provided, however, that if a mininum rate of five counts per second is not achieved during startup, the instrumentation shall be changed so that source range channels shall cover from 2.5 x 10-2 to 2.5 x 103 nv while intermediate 2 nv to 7 x lob v.
n range channelo shall cover from 2.5 x 10 When calibrating scram points on a power range channel non-coincidence scram may be administrative.
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- ne interr.ediate range channels shall initiate a scram in the event of a fast startup when below 10% full power.
The range of use of power level safety channels shall be from 1/, to 7.
150% of full power.
6 Three power level channels shall be provided with a two out of three 8.
coincidence feature to scram the reactor, High power level at startup and high power level at power scrams shall be initiated by these channe)s, An automatic and manual control system shall be provided for positioning Each of the control rods anall have an automatic-off-9.
the control rods.
The rods may be operated individually or in nanual control switch.
The automatic control system shall be designed to handle power groups.
level changes of approximately 2 !M per minute.
H.
MONITORING SY37D3 A radiation monitoring system having the following principal features shall be provided.
The air discharged into the plant stack shall be monitored by beta-1.
ga:ua detectors mounted inside the duct leading to the stack fan.
Activity detected by this monitor shall be recorded and an alarm provided in the main control room.
This monitor shall be in operation l
when the stack fan is energized.
This is not meant to preclude normal calibration of this monitor.
The fission product activity in the main coolant shall be monitored by 2.
a gamma detector located in parallel with the bleed line after the The eersitivity range of this detector non-rege.erative heag exchanger.uc/cc for energies above 0.8 mev.
An alarm l
shall be 10-1 to 10+
shall be provided in the nain control room to alert the operator if _
thiu nonitor exceeds a maximun 15-minute degased activity of 20 uc/cc.
This nonitor shali be in operation (except for calibration and repairs) l
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when the purification system is in operation.
j Detectors shall' he provided to nonitor the containment vessel air for l
3 A small c ount radioactive particulate matter and radioactive gases.
of the containment vessel air shall be drawn through a section of i
i A detector that movin:; filter paper by a constant dispgacement pump.ue/cc shall monitor the filter has a sensitivity range of 10-9 to 10-t A detector that has a sensitivity range of 3 x 10 garticulate matter.to 3 x 10-3 uc/cc in a b paper for beta radioactivity from of 0.6 mr/hr. anall monitor the air withdrawn from the containment vessel.
Alarms shall be provided in the main control room to alert the operator if the particulate nonitor: radioactivity or the gas monitor radioactivity exceeds 25% above equilibrium, power operating, l
backgrouna.
These monitors L.
Six plant area shelf-mounted monitors shall be provided.
snail be located in the waste treatment plant control roon, the reactor plant main cor.trel room, the charging room, the sampling room, the chmical laboratcry, and the health physics office. All of these monitors 'snall have a range of 0-20,000 cpm.
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A gan*.a detector that nas a sensitivity of 0.01 to 10 nr/hr using 5
Cobalt 60 as a reference shall be provided to menitor the steam generator shell side blowdown water to detect any leakage from theAn main coolant system.
room to alert the operator if the radioactivity of the blowdown exceeds 2 x 10-0 uc/ce. A proportional type sampler also shall sample the discharge from the steam generator blowdown tank and a sample shall I
be taxen to the laboratory periodically for counting.
i I.
WASTE DISPOSAL SYSTDG A radioactive waste disposal system having the following features shall be provided:
A purification system having an adjustable flow rate from 3 gpm to 30 gpm This radioactive 1.
shall remove radioactive matter from the main coolant.
matter shall be concentrated on ion exchange resins which shall be Radioactive gas periodically transferred to underground storage tanks. released fro a controlled rate to the atack or shall be renoved by two rotary water-sealed type t,as compressors and temporarily storad in 13) cu.f t.
I gas decay tanks.
Radioactive matter snall be remcVed from the water in the storage well These resins shall be 2.
compartment by means of ion exchange resins.
The nominal transferred periodically to underground storage tanks.
flow rate for this system shall be 15 cpm.
The stack for discharging air-borne radioactivity shall be 125 feet 3
in height.
one 5,0]O-gallon tank shall be provided Two 10,3UO-gallon tanks and h.
to store radioactive water discharged from the main coolant system or radioactive contaninated water from other sources within the plant.
I These storage tanks shall be horizontal, cylindrical tanks mounted Three 800-gallon tanks inside a second horizontal cylindrical tank.
of dual type conctruction shall be provided for storing the spent i
[
Three 133 cu.f t, capacity tanks shall bc denineralizer resins.
provided for the radioactive gas collected by the gas compressors.
l All of these tanks shall be buried underground.
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Radioactive liquids that are above damping tolerance shall be processed throegh a waste treatment plant consisting of a gas stripper and an 5.
evaporator unit, each having a non.inal feed capacity of 1000 pounds per hour.
Concentrates from the evaporator shall be combined with cement inside A wood crib and earth shielded various sice standard steel drum 3.
storare area shall be provi'Jed for storing the filled drums prior to shipment.
No radioactive solid waste shall be buried on the site.
D.
No radioactive liquid waste concentratione in excess of tnose specified in Appendix "B", Tacle II, Column 11,.10 CER 20, snall oe discnarged 7.
to the river.
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e The radioactive concentration of gaseous release, as measured by the B.
radiation monitor in the ventilation duct ahead of the stack fan and after consideration is given to any dilution occurring between the detector and the stack fan, shall not exceed 2.75 x 10-7 ue/cc when The instantaneous gaseous radioactive release averaged over a year.
concentration shall not exceed 2 x 10-3 ue/cc when averaged over a 15-minute period.
J.
VENTILATION SYSTEM 3 The stack fan shall have a maximum flow rate of 30,000 cu.f t, per 1.
minute.
The containnent vessel ventilation system shall consist of the 2.
following major components:
F)ow Rating Unit 10,000 cfh Containment Vessel Air Supply Unit 10,000 cfm Containment Vessel Air Exhaust Unit Air leaving the exhaust uni' is ducted to the stack fan and thence out The radioactive concentration of gaseous activity present the stack.
in this air is monitored prior to entry into the stack fan..
The waste treatment plant ventilation system shall consist of the 3
following major components:
Flow Rating Unit 2,000 cfm Control Hoom Air Supply Unit h,000 cfm Drun Shipping hoom Air Supply Unit 6,000 cfm Exhaust Unit Air leaving the exhaust unit is ducted to the stack fan and thence out The radioactive concentration of gaseous activity present the stack.
in this air is monitored prior to entry into the stack fan, The cor trol and auxiliary building ventilation system shall consist b.
of the following major componentat Flow Rating Unit 8,000 cfm Air Supply Unit 8,000 cfm Exhaust Fan - Main Chemical Laboratory Air Supply Unit 3,000 cfm Chemical Laboratory Hood Exhaust Fan 3,000 cfm Air leaving the exhaust units is ducted to the stack fan and thence out The radioactive concentration of-gaseous. activity present the stack.
in this air is monitored prior to entry into the stack fan.
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w p.DtGDiCY Cv0 LING SYST1K2 K.
Dnergency cooling systems shall be provided for the following conditions:
In case of total power supply failure to the nuclear plant, emergency Steam driven cooling shall be provided for by natural circulation.
1.
boiler feed pumps shall make it possible to intermittently supply water to the steam generator for removing heat from the main coolant t
system.
In case of loss of the stem generator as a heat sink, mergency cooling shall be provided by means of the purification system and ch 2.
i control roon, shall be located in the high pressure charging line to system.
This valve shall nake it possibic tre regenerative heat exchanger.
to by-pass the regenerative heat exchanger and remove heat from the nain coolant system by means of the non-regenerative heat exchanger and the component cooling system.
In the event of a rupture of any part of the main coolant system and a resultant loss of coolant, a safety injection system shall be provided 3.
l to keep the core covered with water containing enough boric acid to naintain the core suberitical by at least 10% K at ambient temperature This system shall_ consist of two with all control rods inserted.
375 gpm mot or-driven centrifugal pumps piped to opere.te individually or in series and discharging into a conmon header and thence to two separate 3-inch pipelines feeding directly into the reactor vessel.
I These pumps shall be in operable condition during operation of the reactor above 1 Mt, except thr.t one pump may be rendered inoperable for the purpose of maintenance for periods not exceeding 7 days.
j Borated water for these pumps shall be supplied from an 80,000-gallon heated storage tank located in the yard adjacent to the containment i
vessel.
A minimum of 2f,000 gallons of berated Nater shall be in this tank These during reactor operation at power levels in excess of 1 Mdt.
pumps may be started manually from the main control room or auto-natically in the event the main coolant systen pressure falls to, A flow control channel for each 1,000 psi or less during operation.of the two lines feeding the reactor vesse main control board so that in the event of abnormally high flow an associated control valve will be automatically closed, thus diverting the flow to the remaining line.
A standby power source to the reactor station shall be provided
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through a 750 KVA, 2300/hh0V transformer from the 2300V station service buses in the existing plant.
In case of failure of the normal power supply which is a 1000 KVA,13 2 KV, 440V trinc-forner, an automatic transfer shall close a broader picking up the I
A I?5V d-c. battery and an inverter-diverter standby power source.
snall provide a standby power supply to an a-c bus used for the vital instruments wnich include nuclear instrumentation, radiation nonitoring, paging system, rod control and position-indication, and process a-c instrumentation and control from the main control room.
.--.,___._.-.,,.._._._,,,.-,-.__._,-,._a._-,..__.,_.-.
a 15.
L.
FUEL STORAGE
.tored in a stainless steel str ucture located in Spent fuel shall bc The fuel component 1.
the storage well in the containment vessel.
storage compartments in the structure shall be arranged ac that individual fuel components are psaitioned in a slab geometry Gnly fuel separated by a minimum of 12 inches, fuel to fuel. assemblies, subass facility shall be stored.
Fuel placed in an AEC approved shipping container, though at the site during transit, shall not be construed as storage of fuel under the 2.
definition in Section L.l.
M.
EXPERIMENTAL FACILITIES The Saxton reactor shall be used in the conduct of a variety of research and These Technical Specifications may be supplemented in accordance with the procedures specified in this license as required for conduct development programs.
of these research and development programs.
ADMINISTRATIVE AND PROCEDtTRAL SAFEGtfARTE H.
Written instructions shall be prepared and will be put into effect for all normal operations, maintenance operations, and emergency operations 1.
which may affect nuclear safety.
Administrative provisions and controls for maintaining nuclear safety 2.
shall be as follows:
hecords such as log books and log sheets will be maintained for all normal operations and testing operations.
System check-off a.
lists and instrument and control set point 11 cts will-be main-All important tained in the main control room at all times.
operating records, including recorder charts, records of radio-activity releases, and any other records required by permits or licenses, will be kept on file for the life of the project.
An AEC--licensed operator will be -in the main control room at all tines while there is fuel'in the reactor, with the exception of b.
periods when no reactivity changes are being made and the reactor is at least $$ subcritical at ambient temperature with the scram circuit _ breaker locked open.
In the event of a. reactor scram, the reactor will not be started up again until the action that initiated the scram can be c.
ascertainea and corrected.
Fbcling, refueling, installation or removal of experimental fuel assemblies or control rods or any other operation that could d.
involve a change in core reactivity will be supervised by qualified 3
t Westinghouse and/or Saxton Nuclear Experimental Corporation personnel.
16e v
All operations that could in any way affect the safet e.
Operation of the Unit No. 2 turbine generator and its auxiliary d in equipment, ss well as other nuclear plant facilities locate f.
ill be the existing Pennsylvania Electric Conpany power plant, w under the jurisdiction of the Saxton Nuclear Experimental Corporation.
Before any major circuit breaker or critical valve can be operated for maintenance or any major piece of equipment, control or i
{
g.
instrumentation can be taken out of service for maintenance, a written permit must be signed by or on the authority of the Reactor Plant Supervisor on duty, A system of radiation work permits will be used to control access ible to areas where radiation over-exposure of personnel is possRadiation h.
by radiation protection personnel will be provided as required within a normal work day.
to minimize exposures.
Radioactive liquid effluents and radioactive gaseous effluents instructions will be discharged to the natural environment only upon i.
The from the Supervisor-Reactor Plant Services or his designee.
discharge of these effluents will then be supervised by the deactor Plant Supervisor on duty.
i For the purposes of Section N, " Reactor Operation" shall be defined am i
that period in which fuel is in the reactor and either (1) the ma n 3
coolant system temperature exceeds 300 F and is pressurized above 0
The " Reactor 150 psia, or (2) the ecram circuit breaker is closed.
Operation" procedures listed below shall be followed:
a.
Startup All personnel will be notified whenever startup of the reactor (1) plant is inminent.
All control rod position indicators will be checked to ascertain that the rods are in the fully ir.serted position except rods (2) cocked for safety purposes.
The following minimum instrumentation will be in operations (3)
(a) Two source ' channels.
(b) Two intemediate channels.
(c) Two. power rance channele.
Pressurizer heatup rate will not be allowed to exceed 2500F (h) per hour.
Differential between main coolant temperature and pressurizer temperature will be maintained less than 2000F and pressurizer l
(5) sprays will not be used if the. differential exceeds 2000F.
i C
l I
2 170 (6) The main coolpnt pressure will not be allowed to exceea 500 psig un+il the temperature of the main coolant is at least 600F above the nil ductility temperature.-
Wnen bringing the main coolant system up to temper ature (7) and pressure, boron removal will not be started before the main coolant system temperature reaches 250 F.
(8) The safety injection controller vill be switched to automatic position when main coolant system pressure.
exceeds safety injection set point pressure by 200 psig.
(9) Whenever the reactor is critical the rod program will be such as to assure a r.hutdown of at least-0.02 upon erava with the most effective rod stuck.
(10)
If the main coolant temperature is below 3500F, the reactor thermal power will not be increased above 1 Mdt.
4 Nhen the main coolant system reaches operating temperature (11) of LBO F, the reactor power may be increased above 10%.
O During the approach to criticality, flux multiplication (12) rates will be maintained at less than one decade per minute.
b.
Operation above 10% full powers (1) A minimum of three power range channels will be in service except that in a condition where one power range channel is inoperative, the reactor can continue to be operated at the existing power level provided no major rod program change is.
carried out and provided the power range high level scram protection is set for single channel operation as specified in Section 0.5.
(2) Feriodic calorimetrin determination for both primary and secondary systems will be performed and the nuclear power channels will be adjusted if necessary.
(3) All annunciator alarms will be acknowledged promptly and abnormal conditions will be corrected as soon as possible.
If the nornal or emergency power supply is lost and cannot (b) be restored promptly,the reactor vill be shut down until such time as both power supplies are in service.
(5) A waste disposal storage tank will be arranged to receive water ejected from the main cool, ant system.
(6)
"'he power level instruments will be monitored as the station load is enanged.
c.
liot' shutdown (1) One control rod group will be left in a cocked pos Ation equivalent to a reactivity of approximately 0.01, except as required to complete system tests and calibrations.
16o g
Tne main coolant system will be maintained at operating (2) temperature and pressure by means of main coolant pump heat, residual heat in core and pressurizer heaters.
A minimum of one source range flux channel and one inter-(3) mediate flux channel will be in service, d.
Cold shutdowns One control rod group will be left in a cocked position equivalent to a reactivity of approximately 0.01 prior (1) to reducing the temperature and pressure.
Before the main coolant temperature reaches h300F, a sufficient amount of concentrated boric acid will be (2) injected to make the reactor suberitical by at least 0.05 at ambient temperature with all rods inserted in the core.
After a suitable mixing time has elapsed, the boron content of the main coolant will be determined by sampling.
The shutdown cooling system will not be put in operation until af ter the main coolant system reaches 300 F and 150 0
(3)
This system will be operated as needed to keep the psig.
main coolant temperature at or below 1h00F, A minimum of one sourne range flux channel and one inter-(b) mediate flux channel will be in service.
4 During " Reactor Operation" (as defined in Section N.3. above) the h.
follo.:ing operating limitatione shall apply:
a.
Containment:
0.4% of the not free volume (1) Maximum leakage rate at 30 psig per 2h hours (2) Vacuum breaker set point 2 in. Hg Vao Closed when reactor is critical (3) Position of valves in the or reactor startup has been ventilation purge lines initiated (b) Maximum containment vessel alarm set points
$ psig (5) Maximum pressure actuating automatic closure of valves in lines between fuel storage well and refueling water
$ psig storage tank b.
Main coolant system:
(1) Maximum 15-minute degased activity in the,sain coolant 20 uc/cc
(
-s 19.
(2) Kir.inum steady-state 1900 poia inlet pressure
- 6200 gre
('J ) 111nimun. flow rate *
(6) Maximum mixed core exit
$60 F temperature *
($) Make-up to reactor pinnt less than 1.0 micro-nho Conductivity per centimeter less than 0.10 ppn Chlorides less than 0.04 pin Silicon dioxide Tower operation above 1 Wt - if any of these limits are (6) exceeded, action will be initiated to bring the condition back within limits.
less than $.0 ppm Inpurities (polids) loos than 0.1 ppn Chloridos less than 0.14 pga Oxygen less thnn 10 pga as boron Boric neid 7
as required to maintain pH Lithium (Li )**
between 7 to 10.5 2 0.5 as neasured at 25 C 1$-90ec/KgofH2 ao measured Hydrogen at S.T.P..
(7) Maximum heatup and ecoldown:
lleatup Cooldown 200F/hr 200 F/nr 0
Reactor vessel 200F/nr 200F/hr 0
Steam generator Prinary plant auxiliary systems:
c.
(1) Prensurit er Maximum hentup and 230 F/hr 3
cooldown rates 2500 pola-Knximum working pressure 668 F Maximm working temperature 20 cu. ft.
- Mininum ligeid volune Haximum relief valve setting 2375 psia Rated total capacity of 63,000lb/hr pressure relief systun Applies only ta' operation above 1 Wt.
Isotopie grade lithium (Li ) of the highest purity should be useo to recuce 7
the production of tritium from Li6 which is present ir, naturally occurring lithium (approximataly 7.5J Li ).
Potassium hydroxide (KOH) is alas 6
satistnetory as a pH adjusting chenical but is includea in the water chcnistry an. an niternato to lithium hydroxide.
l
200 s
d.
Secondary coolant syster.:
(1) Maximum pressure upstream of the pressure reducing station 1800 paia e.
fleactor cores 20 Mwt (1) Maximum power 1cvel (2) Maximum number of fuel 21 assemblico in core 30,000 MWD /MTU (3) Maximum fuel burnup hh0,000 Btu /hr. - ft.2 (h) Maximum heat flux (5) Average heat flux 137,000 Btu /br - ft.2 (6) Minimum burnout safety f actor 2.91 (W-2 correlation) 0 (7) Maximum fuel clad temperature 6h2 F (8) Maximum fuel heat generation 13 3 KW/f t.
(9) Average power density
$h KW/ liter (10) Under credible accident condi-tions as described in the Final Safeguards heport, the minimum burnout safety factor shall be 1.85 (11) Design maximum void coefficient of reactivity at operating
-p.00W% vold temperature (12) Deuign naximum, temperature reactivity defect (cold clean to hot clean) 0.082 (13) Moderator temperature coefficient of reactivity shall not be more positive thans (a) borated at 60er
+1x10-h/0F
-1.6x10-hjoy 0
(b)
Borated at 530 F (c) Unborated at $30 F
- 3 x 10'b/F f.
Control and safety systems Minimum reactivity worth of the six control rods shall be (1) high enough to meet the shutdown requirements stipulated in Section N.3.a.(9) of this specification.
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(2) Maximum reactivity addition rate (six control rods withdrawn simultaneously)
$x10-h/sec.
(3) Maximum cold clean excess 0.26 reactivity (L) Maximum time from scram initiation to scram 1.5 sec.
e Noletion g.
Monitoring systems:
Minimum sensiti/ity of p ant stack monitor 2 x 10-7 uc/cm3 (using Krypton 65 as a reference) whenever air is being discharged from the stack.
The maintenance procedures listed below shall be followed when fuel is 5.
in the reactor, Only authorized personnel will be allowed to enter the centainment a.
vessel to perform inspections and maintenance work. Prior to__
maintenance personnel entering into the containment vessel, radiation protection personnel must have approved the area for When the reactor is in a hot shutdown condition, at least entry.
two men will be sent into the containment vessel whenever it is necessary to make inspections or to performndnor repairs (instrument and equipment adjustments that can be made with hand tools).
At least one person in the containment vessel will have been instructed in radiation protection procedures and will be qualified to recognize any radiation hazard to personnel in the containment vessel.
A minimum of one source range flux channel and one intermediata b.
flux channel will be in service.
Applicable radiation monitoring equipment and alarms will be in c.
service.
The various areas of the plant and compartments in the containment d.
vessel will be monitored for radiation and contamination prior to carrying out maintenance work.
Applicable lines and systems will be sampled for radioactive gases e.
and hydrogen prior to maintenance.
Special clothing will be provided for maintenance work to prevent f.
Other or restrict the spreading of radioactive contamination.
protective equipnent such as filter type breathing apparatus will also be available.
In the case of maintenance jobs performed under radiation exposure g.
conditions which limit the working period, special check lists and procedurer, will be developed and the personnel involved will.be thoroughly briefed prior-to entry into the work area.-
dt.
.c The nochanical interlock in the air lock may ba by-passed and the o~uipwnt accese door may be opened if the following conditions h.
are
- rmafied:
(1) The scram breaker is locked open, and (2) No reactivity iasertion such as additions of fuel or removal of boron or control rods will be nade, and (3) The main coolant is less than 150 psig and 300 F, and
( f.) The reactor is suberitical by at least 0.05.
During refueling, control rod replacenent, or any maintenance operation 6.
that could involve a change in reactivity with a port in the reactor vessel head open or with the head removed, the procedures listed below shall be followed:
An AcC licensed operator will be present in the control room and an AEC licensed senior operator will be present at the facility.
n.
Personnel adequately trained in the fueling operation will alr.o _ be precent in the containnent vessel to supervise this operation.
Once the addition of fuel to tne core has begun, no operation vill b.
be performed which will reduce the boron concentration in the main coolant system, Fuel will be loaded one asambly at a tiac and inverse count rate data will be taken and evaluated after each assenbly is loaded.
c.
If at any tine the experimentally extrapolated value for the etitical size of the reactor core (as indicated by the 1/H data from any det ecto-) is less tm two fuel assemblies plus the number of fuel assemblien 'thn* In the core, the loading operation will be suspended until a cWufactory evaluation of the situation can be made, In the case of the removal of an individual control rod, the four d.
adjacent fuel assemblies will be removed first.
A mininum of two source range flux channels and two intermediate range flux channels will be in service during these operations.
c.
Applienb'.e radiation monitoring equipnent and alarms will be in f.
service during these operetions.
Westinghouse and/peration will be supervised by qualified The naintenance o c.
or Saxton Ih. clear Experimental Corporation personnel.
Sufficient baron will be added to the main coolant to maintain h.
the reactor suberitical by at least 0.05 except any time the reactor vessel head is removed at which time the reactor will be cuberitical by at least 0.10 with a fully loaded rodded core at ambient temperature.
i
. e 25.
4 7.
During emergencies, the procedures listed below shall bc _ followed:
a.
In case of high radioactisity level in the containment vessel indicated by either the air particle detector alarm or radio-active gas detector alarm, the reactor will be shut down.
The inst ruments may be checked for proper operation and the condition promptly verified with a portable monitor or air sample to confirm that shutdown action is required. The purge system will be put into operation if the stack discharge activity will not exceed the levels specified in Sect ion 1.8.
If this action does not reduce the radioactivity level, a reactor shutdown and/or cooldown will be initiated.
b.
If the stack radioactivity alarm is actuated, the various possible sources of radioactivity will be shut off sequentially if this action does not remedy the condition, the reactor will be shut down or cooled down as the case may be.
The inst rument may be checked for pro 7cr operation and the condi-tion promptly verified with a portable monitor or air sample to confirm that shutdown act2on is required.
I f the steam generator blowdown radioactivity alarm is actuated, c
the blowdown will be discontinued promptly and a blowdown water sample will be checked for radioactivity, d.
If the radioactive alarm in the liquid offluent line to the river is actuated, the valve in this line will he closed promptly.
e in case of high coolant _ 15-minute degased radionctivity above 20 uc/ce, the purification system flo,v will be increased arid if thi s does not help to reduce the radioactivity in two hours, the reactor will be shut down.
f Operating instructions will be prepared for emergencies such as loss of coolant. loss of coolant flow, cont rol rod mal function, loss of stcar load, f ailure ut reactor cont rol circuit, and uncontrolled heat c st ract ion and these instructions will enumerate t he aut omatic ac tions that should occur and also list the inmediate manual act ions t hat t he operator should take,_
In all emergencios, 2 f the automatic cont rol does not shut down the reactor when it should, the opurator is instructed to shut down the reactor by e
eit her manual scram or by runninr in the control rods.
8 Test spect ficat ions a.
Containment pertodic test ing.
(1)
As an interim measure prior to adopt 2ng a comprel,iensive leak-age rate testing program and schedale for the containment system, an integral leakage rate test shall be conducted oti t he containment vessel within 90 days of the effect ive date of the Itcense at the desinn pressure or at such lowcr pres-sure as may be agreed upon by the Commission.
Saxton shall I
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24.
l submit to the Commission within 30 days of the scheduled time a description of the test method and procedurcs, for the test including the test pressure and duration of the test, the method of measurement of leakage and extrapolation between test The integral leakage rate test pressure and design pressure.shall be repeated at approximately two-year in the comprehensive Icakage rate testing program and s,hedule for c
system shall have been developed and hdopted.
the containownt I
b.
tbjor systems:
Major systems and controls shall be tested in accordance with the following schedule:
Safety ir.)cet ion pumps ind automatic startup control hbnthly Monthly Radiat ion moni;ar circuits Cont rol rod drive 2. cram speed Every 6 months Scram circuit response time Every 6 months measurement l
No. 2 turbine overspeed trip Every 6 months Nuclear instrumentation Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to each startup calibration Prior to any startup after a 24-hour Scram circuit operational test or greater rhutdown After repairs or modification Main coolant system hydro test affecting the strength of this sy stem All visible surfaces will be -
Reactor vessel and main coolant inspected during refueling or system inspection any timo the main coolant system is open for maintenance.
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o Supplement No.1 to Technical Specificatione Incorporating Changes Applicable to Conduct of Phase I of the Saxton Pive-Year Research and Development Program During the conduct of tests and experiments contained in the Phase 1 Researen and Development Program, the technical specifications shall be changed to the extent indicated below. Except to the extent as changed, all of the
)
remaining provisions of the technical specifications shall remain in effect.
Saxton shall advise the Commission in writing upon termination of the Phase I Program.
Item references below are to the technical specifications constituting Appendix "A" to operating License DPR-h.
Change Section N.h.b Primary coolant system:
(1) Maximum 15-minute degased activity in 20 uc/cc the main coolant 1900 psia (2) Minimum inlet pressure
- 6200 gpm (O Minimum flow rate
- w) Maximum mixed core exit temperature
- 0 560 F (a) Rod shim 0
$$0 F (b) Chem shim (5) Make-up to reactor plant
_less than 1.0 micro-mho/cm Conductivity less than-0.10 ppm Chlorides less than 0.0h ppm Silicon dioxide Power operation above 1 Kdt - If the following limits are exceedide accion (6) will be initiated to bring this condition back within limits.
-less than 5.0 ppm-Impurities less than 0.1 ppm Chlorides less than 0.1h ppm Ox/ gen a maximum of 2500 ppm as boron Boric acid as required to maintain the calcu-Potassium and/or lithiam lated hot pH between 7_ and 10.510.5 15-90 cc/Kg of H O as measured at S.T.P.
2 Hydroger;
- Apply only to operation above 1 Kdt.
'T 2.
Maxinum heatup and cooldown rates shall be as follows:
(7)
Heatup Cool _down 0
200 F/hr.
200 F/hr.
0 Reactor vessel 200 F/ta.
0 200 F/hr.
0 Steam generator Change Section F.2.
Uranium oxide (UO2) enriched to 5 7% of U-235 shall be used in th assemblies, except that the test fuel assemblies listed below having enrichments as described may be inserted in the reactor.
Test Fuel Test Fuel Test Fuel Assembly No. i Assembly No.ii Assembly No.iii
~ )-Rod Hollow y-Rod Sub-9-rtod Sub-o assembly Assembly ___, and assembly or First 1h pellets 5.69%
5 69%
5.69%
Next 2 pellets 7 30%
9.19%
7 30%
6.81%
6.81%
6.57%
Next 3 pellets 8.13%
6.h6%
6.h6%
Next 12 pellets 8.57%
6.81%
6.81%
Next 3 pellets 9.19%
7.30%
Next 2 pelleta 7.30%
5.69%
Next ih pellets 5.69%
5 69%
i The 9-rod subassembly in the second column shall not be used at NOTE:
reactor power levels greater than 20 Kdt.
l Test Fuel Assembly No. iv One 9-rod subassembly sh&ll have four corner rods clad with Zircaloy-h having
(
a nominal thickness of 23.7 mils and shall contain uranium oxide (UO 2
The otner five rods shall be clad with Type 30h stainless steel having a nominal thickness of 9.$ mils and shall contain uranium oxide (UO )
to 6.1% U-235.
2 enriched to 5 7% U-235 Test Fuel Assembly No. v One Y-rod subassembly shall have four corner rods clad with Zircaloy h. having 2
hd a nominal thickness of 23.7 mils and shall contain uranium oxide having a nominal thickness of 9.5 mils and-shall contain uranium oxide (UO )
to 6.1% U-235 2
having the same enrichment as Test Fuel Assembly No, i.
Test Fuel Assembly No. vi_
One L-rod sub ssembly shall have rods clad with Type 30 l
2 One of these rods may contain fuel pellets uniformly enriched to 8.3% U-235 up to 100* ppm boron as zirconium diboride.
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Test Fuel Assembly No. vii One 9-rod subarsembly sha'.1 have the center tod and four corner rods clad with Zircaloy-4 having a nominal thickness of 23.7 mils and shall contain uranium oxide (UO ) uniformly enriched to 7.31.
Two of the other rods shall be clad 2
with Type 304 stainless steel having a nominal thickness of 15 mils and shall contain uranium oxide (UO2) uniformly enriched to 5.7% U-235. One other rod shall be clad with Type 304 stainless steel having a nominal thickness of 16.1 mils, shall contain uranium oxide (UO2) having a content of 0.29% U-235, and shall be concentrically located within a solid stainless steel guide tube.
The remaining rod shall be clad with Type 3C4 stainless steel having a nominal thicknese of 16.1 mils, shall contain uranium oxide (UO ) having a content of 2
0.71% U-235 and shall be concentries11y located within a perforated stainless steel guide tube.
Uranium oxide at the density being used has a melting point of approximately 50000F.
Add Section F.4.
One 9-rod subassembly may be used having uranium oxide (UO ) fuel in pellet 2
gorm enriched to 6.1% U-235 with cladding of Zircaloy-4.
Change dection N.4.e.
(1) The steady-state reactor power level shall not exceed the following:
20 MWt (a) with rod shim control (b)
With chemical shim (boric acid solution) control 23.5 MWt 21 (2) Maximum number of fuel assemblies in core (3) Maximum fuel burnup, HWD/MTU 30,000 (4) Maximum heat flux spiked region, Btu /hr. ft.2 533,000 (a) 4-rod spiked subassembly, Btu /hr. ft.2 444,000 (b)
(c)
Unspiked region, Btu /hr. ft.2 470,000 g
(5) Average heat flux, Bcu/br. ft.2 161,000 (6) Mintaum steady-state burnout safety factor (W-2 correlation) 2,27 (a) dpiked region 2.64 (b) Unspiked region (7) Maximum fuel clad temperature, OF 642 4
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(S) Maxinun fuel heat generation (a) In 63-rod spiked hollow assembly and 9-rod 16.0 spikedsubassembly,kw/ft.
20.0 (b) In h-rod spiked subassembly, kw/f t.
IL.1 (c) Inunspikedregion,kw/ft.
63.5 (9) Average power density, kw/ liter of core Under credible accident conditions as described in Saxton's Safeguards Report (10) for Phase I, the minimum calculated burnout safety factor in any channel, except the closed L-rod subassembly, is not expected to be less than 1.35 If a loss of coolant flow accident occurs, the b-rod
('d-2 correlation).
C subassembly shall be examined, or an analysis shall be made based on actual flow coastdown characteristics to demonstrate that no deformation occurred.
(11) Design maximum void coefficient of reactivity
- 0.001h/% void 3
at operating temperature (12) Design maximum temperature reactivity defect 0.082 (cold clean to hot clean)
(13) Maximum moderator temperat.ure coefficient of reactivity shall not be more positive than
+1x10-h/0F (a) Borated at 800F
- 1.6 x lO-hjoy (b) Berateu at $300F
- 3 x lO-hjoy (c) Unborated at $300F Change Item G.3 The reactor shall be automatically scrammed under the following conditions:
Set Point Conditions (Maximum) 2 decades / min.
Fast startup rate (Maximum) 25% full power Righ power level at startup High power level at power 20 Mdt operation (Maximum) _
2h Mdt 23.5 Kdt operation (Maximum) 2? Mdt (Minimum) 1600 psig Iow main coolant pressure 6 lb/hr.
Low main coolant flow above 1 Mdt (Minimum) 2.2 x 10 Low water level in pressurizei (Minimum) 8.3%
Contact on breakers, failure of f
Loss of main coolant pump power power supply, or loss of variable frequency set clutch excitation when variable frequency set is supplying power for main coolant pump operation High main coolant temperature (hot leg) (Maximum) 3$h0F
- - - - - ~ ~ - - - - - -
50 Add Item N.3.b.(7)
During the chemical shim control tests, periodic measurements of the core resctivity shall be made. The total unexplained reactivity loss, including measurement and colculation uncertainties, shall be limited to a value such that release in the manner postulated in Section V.B.5. of the Safeguards Report for Phase I does not exceed the accident criteria set in Section V.A.2.
In performing the computations to determine this reactivity value, the experimentally determined core characteristics will be used when svailable, otherwise analytically determined parameters shall be used.
If the unaccounted for reactivity reaches the above limit, the experiment shall be discontinued and an evaluation instituted.
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l UNITED STA"cES ATOMIC ENERGY COMMISSION
\\
SAXTON NUCLEAR EXPERIMENTAL CORPORATION L
DOCKET MO. 50-146 i
NOTICE OF ISSUANCE OF OPERATING LICENSE Please take nottce that no request for a formal hearing having been filed following publication of the' notice of proposed action in the Federal Register, the Atomic Energy Coasaission has issued Operating License No. DPR-4 to.Saxton Nuclear Experimental Corporation, authorizing Saxton to operate at thermal power levels to 23.5 megawatts its light water moderated and cooled, pressurized water reactor located near the Borough of Saxton in Liberty Township, Bedford County, Pennsylvania. The reactor has been operated under Provisional Operating License Fo. DPR-4 issued to Saxton NovemLer 15, 1961.
The license issued is a full term license with an expiration date of j
April 13, 1967, and is as set forth in the Notice of Proposed Issuance of Operating License published in the Federal Register on January 30,1964 29 FR 1594 FOR THE ATOMIC: ENERGY COMMISSIQN-Original signed by, R. Lowenstein -
Director -
Division of Licensing and Regulation Dated at Betnesda, Maryland this-day of 1964.
FEB 2 91904 j
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