ML20085C517
| ML20085C517 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 06/09/1961 |
| From: | Neidig R SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110020306 | |
| Download: ML20085C517 (28) | |
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Id SAXTON NUCLEAR EXPERDertAL CORPORATIM Appl'ication for Reactor Constntetion Permit and Operating License Docket No. 50146 Amenthment No. 6
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- yot is.iv The purpose of this amendment is to sulait to the Commissions (a) Proposed technical specifications to be incorporated as an attachment in Saxton's operating license, and (b) Propused definition of the Baxton "faaility" for inclusion in the operating license.
BAXTON NUCLEAR IIFERDerIAL CORPORATION By /s/ R. E. Neidig Pa sident Attent (G E A L)
/s/ E. L. Barth Seentary Sworn and subscribed to before as this 9th day of June 1961.
(S E A L)
/s/ Martin A. Kohr Botary Public, Muhlenberg Township,Berks County ltr Comunission Empires February h,196?
9110020306 910424 PDR FOIA DEKOK91-17 PDR w _ _ - - _ - --
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l ,e SAXTON NUCLF.AR EXPERIMDITAL CORPORATION L
TECHNICAL SPECIFICATIONS The following technical specifications pertain to the Saxton Nuclear Experimental Corporation nuclear steam generating facility. Descriptions
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of facility components include in a n aber of instances values which are i
i intended to describe the design capacity or calculated operating conditions ,
l of such ccamponents and which are expressly stated to be " design" or .
" calculated" values. Some ' deviation frcan design and calculated values is '
to be expected in actual operation of the facility due to manufacturing and other tolerances. Further, operation of certain camponents at -
levels above or below the stated design capacity or calculated operating conditions vill not necessarily affect the safety of the facility. Accord-ingly, deviations frcan stated % sign" capacities and " calculated" operating conditions will not involve a change in these technical specifications unless ,
such deviatione (a) could reasonably be considered to affect the safety of plant operation or (b) result fresa a physical change in the facility se described in these technical specifics.tions.
- 1. The facility is located on the-Barton Steam Generating Statics 1 property of the Pennsylvania Electric Ccanpany near the Borough of Saxton, t Pennsylvania, in Liberty, Township, Bedford County, Pennsylvania. The Pennsylvania' Electric.Ccunpany property consists of approximately 150 4 acna along the.Raystown Branch of the Juniata River and the minimum ,
distance frcan the center of theicontsizment vessel to the neanst boundary including the river. is 805 feet. De principal activities carried on within this property are the generation and transmission of
- electric power by the Pennsylvania Electric Ccuspany and the preparation q
i l 2-and snie of ashes from an ash dump located at the eastem end of the property.
- 2. The containment vessel design pressure is 30 psig and the maximum total leakage rate including penetrations is 0.2% of the free volume in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at design pressure. A test to confim the containment vessel and penetrations leakage rate shall be made at not less,than 10 psig within one year from the time the full tem operating license is issued.
The personnel entrances to the containment vessel have double door air locks that are mechanically interlocked to prevent both doors frczn being opened at the same time. A mechaniam requiring a mycial tool or key is provided to override this interlock under certain conditions which are given under maintenance openting procedures in these technical specifications.
The containment vessel dimensions, materials of constructica, free volume and containment vessel' penetation infomation are given in Subsection 223oftheFinalSafeguardsBeport(Figuns 201-3, 201-4, 201-5, and 201-6 and Buosection 506 that are refernd to in subsection 223 are not included as a part of these technical specifications.)
Provision has been made for a total of 325 electrical penetrations and 87 piping penetrations including spares. There are approximately 150 span electrical penetrations and 40 span piping penetrations. During
- operation when the containment vessel is closed, the intemal pressure vill be maintained at essentially atmospheric pnsaure.
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3-3 One main coolant systern consisting of one Type 304 stainless steel piping loop, one reactor vessel, one canned rotor pump, or.v ?. team generator, and one pressurizer are being provided. The reactor vessel design features in$1uding pressure rating, materials of .
construction, overall dimensions, types of connections and number of penetrations am given in paragraph B on page 204.2 of the Final Safeguards Deport.
The main coolant is demineralized light water containing boric acid as requimd for reactivity control. The maximum permissible activity of the main coolant shall not be more than 20 ue/cc of long-lived isotopes. ' main coolant shall make one pass through the core in an upward direction. The main coolant design openting variablesunder steady state conditions an as follows:
(a) Minimum inlet pressun 1935 psia (b) Flow rate 7250 spa (c) Mixed core exit temperatum 540 F The principal features of the major components an as follows:
(a) The steam generator is a vertical shell and U-tube type with integral steam drum and three stages of moisture sepantion.-
This steam generator is designed with 40% excess capacity above the nominal 20 MW rating of the core.
(b) The maximum primary safety valve setting is 2575 Psia.
(c) The total capacity of the pressun relief sys. tem is 65,000 lb/hr of saturated steam.
(d) The purification system,has a maymum 6esign ficnr rate of 30 gpa and is designed to maintain the impurity level of the main coolant 1 i
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vater at less than 1 pin with a flow rate of 10 gyn. Operation of the plant is natisfactory up to 5 p}n solids.
(e) A saapling system is being provided to periodically sample main coolant on the discharge side of the primary coolant pump, pressurizer vater, and inlet and outlet of the purification and borie acid demineralizers.
(f) The primary shield is described in Subsection 221 of the Final Safeguania Report. (Details shown on drawings 201-3, 201-4, 201-5, 201-6, 201-7, and 201-8 referred to in Subsection 221, except for shield dimensions, an not a part of this technical specification.
- 4. The secondary coolant is light water and steam. The calculated operating pressure vill be approximately 605 psia vhen transferring 20 MWT. The maximum permissi,ble pmesure upstnam of the pressun reducing valve is 1800 psia. The **v4=nna temperature vill be the saturation temperature for the steam pressure developed. The steam flow rate vill be approximately 69,000 lb/hr at 20 MVT and 97,000lb/hrat28MWT.
5 A reactor core having the following features is provided (a) The main coolant, which is liFht vater, vill serve as the moderator and reflector. The effective reflector thickness is 10 inches.
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(b) Uranium oxide enriched to 5.'$ U-235 vill be used for fuel.
Uranium oxide at the density being used has a melting point of approximately 50000 F.
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. I (c) Type 30!4 stainless steel is used for the cladding of the fuel assembly rods that require no further welding or brazing. Type 3kB modified carbon stainless steel is i
- used for the L-shaped fuel assemblies. The melting point of stainless steel is approximately 2550 F.
(d) The fuel element description and dimensions are given on i pages 2031, 203 2 and 203 3 of the Final Safeguards Report.
(The ntonber of fuel rode in the core, the number of fuel pellets per fuel rod, fuel" pellet and pel'.et column dimension tolerances, fuel rod end gap dimensions, and the total weight of UO2 in the reactor core as given on these pages are not a part of this technical- specification.)
(e) The maximum total weight of' fuel in the core is approximately -
2250 lbs of UO2 enriched to 5 7 weight per cent U-235 isotope.
(f) The maximum number of fuel assemblies in the initial core is 21. .
l (g) The fuel element design is based on an average fuel burnup of 7300 MWD /MTU.
(h) The **v4=m calculated void coefficient of reactivity is -0 39% k/$
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(1) The calculated temperature reactivity defect is 8.2% k from cold l clean to hot clean conditions at zero power.
(j) Boric acid will be injected into the main coolant system'to-maintain the reactor suberitical by at' hast 3% k when all.the control rods are inserted and the main coolant' temperature'is less-
- thanA30 F.
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4 During initial core loading, refueling, or during any movement of the ccatrol rods or fuel assemblies with the reactor vessel head off, sufficient boric acid vill be injected to maintain the core suboritical by 10% h vitn all control neerted.
The boric acid system consists of a 50 cc. r . ' capacity steam-heated tank for preparation of the concentrf. ten boric acid and a 30 gpm stainless-steel boric acid pump and piping for transferring the boric acid to the charging system which is used to inject the boric acid into h main coolant system.
(h) The fuel cell vater to uranium ratio is 4 6.
(1) The principal core temperacures and themal characteristics at 20 MWT under steady state conditions an as follows:
Marimum calculated hent flux, Btu /hr-ft2 444,000 Averageheatflux, Btu /hr-ft 2 137,000 Minimum burnout safety factor 2.4 Maximum ca'.v uated fuel clad temperature, F 6h2 MaximumfuelheatgenerationXW/ft 13 3 Average power density, KW/ liter, core 54 (m) Under transient conditions, the minimum calculated burnout safety factor is not expected to be less than 1.15
- 6. The reacter control and safety system has the following features:
(a) There vill be a total of 6 offset cruciform-shaped control rods.
The minimum number of operative control rods is six. 'the control rods and control rod drive mechanisms are described in paragraph D of Subsection 203 of the Final Safeguards Report. (Details shovn' on Figures 203-5a and 203-5b referred to in this-paragraph are not part of this technical specification.')
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(b) The maximum chleulatd reactivity vorth of the six control rods at an operating temperature of 530 0 F is 24 k.
(c) The maximum calculated nactivity worth of any control rod groupiscalculatedtobe12%k.
(d) The minimum scram control margin at operating pmasure and '
temperature with one control rod stuck is 2% k.
(e) Tne maximum calculated reactivity addition rate if all six control rods an withdrawn at operating temperature at the
. maximum withdraval rate of 1 5 inches per minute is 5 'A 1 Vb k/sec. .
(f) The maximum calculated excess reactivity when the reactor is coldcleanis25%k.
(g) The nactor vill be autcanatically scransned under the folloring conditions:
Condition Sei Point Fast startup rate 2 decades / min High power level at startup 5W High power level at power 24 W Lov main coolant pressure 1600 psig Lov main coolant flov 1.8 x 506 lb/hr Lov vater level in pressurizer 10 inches
, Loss of main coolant pump power Contact on bn akers High main coolant. temperature (hot leg) 6000 F (h) The fonoving interlocks an provideat h Function- Candition of Use Electrical Limit the average re. Automatic during all (adjustable naistors) activity insertion rate operations l
to a mad aus of 8.2-x 10~) k/sec.
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M Function Condition of Use Electrical Limit rod withdravnl to Adjusted periodically (relay on position in- provide 2% shutdown based on rod vorth I dicator coils) margin with one stuck curves and operating
! rod. conditions.
Electrical Remove startup rate rod Automatic during stop and scram above startup 10% power.
Electrical Prevent autcmatic oper- Automatic during startup ation of control rods and drops in power belov 10% power.
l (1) The following by-passes or overrides are provided:
By-pass Method Condition of Use Source range Manual switch on control Power operation channegsabove board 5 x 10 ny l
Power range Manual switch on control Below10%powerand channel coinci- board when any pover range dance channel is not operating l Startup power Manual switch on control When power level exceeds l
level scram board 10%
Lov mait eccio .c Puch button on control During startup or t of pressarize conso?e. (Selfreset cooldown l pressure nbove1600 psia)
Safety ir jection Manuaa. switch on control During startup, cooldown board or testing of safety in-jection pumps (j) The range of use of the startup rate scram is 2 5 x 10 ny to 7 x 100nv vhere 7 x 10 0nv is equal to 10% of full power (20 MW).
(k) The maximum total scram delay time is calculated to be 0.465 seconds. The maximum calculated control rod insertion time is ceJeulated to be 0 75 se:onds.
l (1) The minimm numbe'r of operative power level safety channels is 2.
The range of use of power level safety channels is from 1% to 150%
of full (20 MW) power. These channels are in selvice during startup as well as during power operation. The minime number of startup t
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rate channels is 2. The range of these channels it from 2 5 x 102 ny to 7 x 100 nv vhere 7 x 100 nv corresponds to 10% of full power (20 MW).
(m) The vorth of control rods cocked during startup is 3%.
7 A standby power source to the reactor station vill be provided through a750KVA,2300/40 y transformer from the 2300 y station service busses in the existing plant. In case of power failure from the normal power supply, which is a 1000 KVA,13 2 Kv/440 y transromer, an autatatic transfer vill close a brec.her picking up the standby power source. A 125 y d-c battery and an inverter-diverter is provided to supply power to an a-c bus used for the vital instruments.
- 8. A radiation monitoring system having the following significant features is bein6 provided.
(a) The air discharged into the plant stack is continuously n onitored by four thin-valled, Geiger-Mueller tubes operated in parallel.
These detectors am mounted in a velded steel pipe frame inside the duct leading to the exhaust fan in the base of the stack.
The minimum sensitivity of these detectors is 2.0 x 10'I ue/cc.
Any activity detected by this monitor is recorded and alarmed in the main control room.
(b) The iodine activity in the main coolant is monitored by a detector located in the bleed line after the non-regenerative heat exchanger.
The detector consists of a cation bed in series with an anion bed with a photomultiplier tube and scintillation crystal gamma detector mounted on the anion bed. The sensitivity range of this detector is 2 x 10-b to 2 x 10~1 ue/cc for energies above 0.8 mev.
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(c) Detectors are provided to continuously monitor the containment vessel air for radioactive particulate matter and radioactive gases. A small amount of the containment vessel air is continu-ously drawn through a section of moving filter paper by a i
constant dispincement pump. A lead shielded, end-on phosphor photmultiplier detector monitors the filter paper for beta radioactivity from particulate matter. Tne sensitivity of this detector is 10*9 to 10-6 uc/cc. The radioactive gas detector, which continuously samples the air withdravn from the contain-ment vessel, is a one-foot diameter sphere which contains a photomultiplier and scintillation crystal. The sensitivity of this instrument is 3 x 10*b to 3 x 10-3 ue/ec in a background of ,
0.6mr/hr.
(d) Six plant area shelf-mounted monitore are provided. These monitors are located in the vaste treatment plant control rom, the reactor plant main control room, the charging room, the .sampiing rom, the chemical preuration laboratory, and the health physics office. All of these monitors have a sensitivity range of 0.01 mr/hr to 10 nr/hr, except the monitor in the main controlroomwhichhasasensitivityof0.2mr/hrto200mr/hr.
The plant shielding has-been designed to limit the radiation levels in tne various areas as follows:
Continuously occupied areas (such as main control room) 0.25mr/hr Intermittently occupied work areas (such as vaste treatmentbuildingcontrolrom) 075mr/hr
.Intemittently occupied ground level areas during operating (such as areas ad,)acent to containment vessel) 2.0mr/hr Containment vessel dtxing refueling optrations 2.0mr/hr
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(e) A detector is provided to continuously monitor the steam generator shell sidv blovdown water to det:ct any leakage frce the main coolant system. This detector consists of one minimum gamma sensitivity Geiger-Mueller detector used in a cylindrical tank which surrounds the detector with approximately one cubic foot of liquid. A proportional type sampler continu-ously samples the discharge from the steam generator blevdown tank.
9 A radioactive vaste disposal system having the following features is being provided.
(a) A purification system having an ad,)ustable flow rate from 3 spn to 30 gpm vill continuously remove radioactive particulate matter from the main coolant. This radioactive particulate matter vill be concentrated on ion exchange resins which vill periodically be transfer.md to underground storage tanks. Radioactive gas released in the purification system surge tank sill be removed by a gac disposal system consisting of two rotary water-se,aled type gas compressors and three 133 cubic feet gas decay tanks.
(b) Radioactive particulate matter vill be continuously removed from the water in the reactor and storage vell compartment by means of ion exchange resins. These resins vill also be periodically trans-ferred to underground storage tanks. The nomital flow rate for this system is 15 gpm.
(c) The stack for discharging air-borne radioactivity is 125 feet in height. The exhaust fan discharging into this stack has nominal capacity of 25,000 cfm.
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- (d) Two 10,000 gallon tanks and one 5,000 gallon tank are provided to store radioactive water discharged from the main coolant system or radioactive contaminated vater from other various sources within the plant. These storage tanks are horizontal, cylindrical tanks mounted inside a second horizontal, cylindrical tank. The tank-vithin a tank design provides an annular space for detecting and-monitoring leakage. Three 800 gallon tanks of the dual type ,
construction vill be provided for storing the spent demineralizer resins. Three 133 cubic feet capacity tanks are provided for the radioactive gas collected by the gas empressors. All of these tanks are buried underground.
(e) Radioactive liquida vill be processef.through a vaste treatment plant ccasisting of a gas stripper and an evaporator unit, each having a usinal feed capacity of 1,000 pounds per hour. All-a of this equipment is constructed of Type 30l+ stainless steel and the evaporator includes an evaporator still pot, demister, and vent condenser. Concentrates from the evaporator vill be cabined with cement inside varicas size standard steel drums. A wood crib and earth shielded storage ana is provided for storing the filled drums prior to shipment by an AEC licensed carrier.
- 10. Emergency cooling systems are provided for the following conditions.
(a) In case of total power supply failure to the nuclear plant, emergency cooling vill be provided for by natural circulation.
Steam-driven boiler feed pumps make it possible to intermittently suppky vater to the steam genemtor for removing heat fra the main' coolant system.
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l (b) In case of loss of the steam generator as a heat sink, emergency cooling can be provided by means of the purification-system and charging system. A by-pass valve, that is remotely controlled fra the main control rom, is located in the high pressure main coolant line to the regenerative heat exchanger. This valve makes it possible to by-pass the regenerative heat exchanger and remove heat fr a the main coolant system by means of the non-regenerative heat exchanger and the component cooling system. During this period, the flow rate can be increased to at least 30 gpn and a total of approximately 1,800,000 BrU per hour can be removed.
(c) In the event of h rupture of any part of the main coolant system and a resultant loss of coolant, a safety injeci;1on system is provided to keep the core covered with borated vster. This system consists'of tvo 375 gpn motor-driven centrifugal pumps piped to operate individually or in series and discharging through two separate 3-inch pipe lines directly into the reactor. vessel.
Borated water for these pumps is supplied from an 80,000-gallen heated storage tank located in the yard adjacent to the contain-ment vessel. These pumps can be started manually from the main control rocan or would be started autcanatically in the event the main coolant system pressure falls to-l',000 pai or less-during operation. A flow control channel for each of the two lines feeding the reactor vessel is mounted on the mein' control board.
In case cme of these lines ruptures, the flow in the line vould-bec ue abnormally high. This vill be detected by_the flow control channel and an associated control valve vill be autcnantically.
closed,_ thus diverting the- flow to the remaining lire. .
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- 11. Administrative and procedural safeguards: ,
(a) Detailed written procedures vill be prepared and vill be put i
into effect for all normal operations or emergency operations which may affect nuclear safety.
(b) Administrative provisions and controls for maintaining nuclear safety are:
(1) Records such as log books and log sheets vill be maintained for all nomal operations and testing operations. System check-off lists and instrument and control set point lists vill 'be maintained in the main control room.at all times. .
All important operating records, including recorder charts, records of radioactivity releases, and any other records-ruquired by pemits or licenses, vill be kept on file for i
the life of the project.
(2) An AEC licensed operator vill be in the main control rom i at all tboes while there is' fuel in the reactor, with the-l l exception of periods when the -reactor-is ~at leas.t 5% sub-l critical at ambient' temperature with all control rods inserted and the control rod drive mechanism controls locked out..
(3) In the event of a reactor scram, .the reactor vill not be started up again until the. action that initiated-the scram-can be ascertained;and corrected. If the trouble cannot be-located imediately or if cornetive action cannot be taken by means -of supervisory instruments and controls in the main' control roca or equipnent that is. accessible outside the :
containment vessel, the Supervisor _of Operations and Tests or the Nuclear Plant Superintendent vill _ be notified immediately.
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, One of these supervisors, or a supervisor of equivalent qualifications, will always be on call for such emergencies.
(4) Fueling, refueling, and the installation or removal of experimental fuel assemblies or control rods vill be super-vised by qualified Westin6 ouse h and/cr Saxton Nuclear Exper-imental Corporation personnel.
(5) All operations, that could in any way affect the safety of the plant, vill have to be cleared with the Recetor Plant Supervisor on duty.
(6) Operation of the Unit No. 2 turbine-generator and its auxiliary equipnent, as well as other nuclear plant facilities located in the existing Pennsylvania Electric Cocmany power plant, vill be under the jurisdiction of the Saxton Nuclear Experimental Cor-poration.
(7) Before any major circuit breaker or critical valve can be operated or any major piece of equipnent, control, or instru-mentation can be taken out of service, a written order must be issued and signed by or on authority of the Reactor Plant Supervisor on duty.
(8) A system of radiation vork pemits vill be used to control access to areas where radiation overexposure of personnel is possible within a normal work day. Radiation monitoring and assistance by radiation protection personnel vill be provided as required to minimize exposures.
(9) Radioactive liquid effluents and radioactive gaseous effluents vill only be discharged to the natural environment upon instruc-tions from the Supervisor - Reactor Plant Services er his
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l designee. The discharge of these effluents vill then be supervised by the Reactor Plant Supervisor on duty.
- 12. Principal operating procedures having a potential effect on safety are listed below.
(a) Initial core loading: C (1) An AEC licensed operator is present as well as personnel adequately trained in the fueling operation.
(2) Sufficient boron has been added to the main coolant to render the core 10% suberitical with a funy loaded, rodded core.
(3) One control rod group vill be cocked for safety purposes.
(4) Once the additien of fuel to the core aas begun, no operation may be performed which vill reduce the boron concentration in the main coolant system.
(5) If at any time the experimentally extrapolated value for the critical size of the reactor core (as indicated by the 1/M data frm any aetector) is less than two plus the number cf assemblies then in the core, sufficient boron vill be added to satisfy this condition.
(6) Four BF3 hannels vill be used f r 1 ading; f these, three ,
must always be functional.
(7) No more than one nuclear detector vill be reir>cated between any two data steps.
(8) Should the loading operation be interrupted for a period of more than two hours, a new set of data must be taken before a new loading adjustment is made. If the new data deviate by mo.e than 20% fra the corresponding previous data, the last
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loading step involved in the addition of fuel must be repeated and the extrapolation to criticality checked.
(b) Initial criticality:
(1) Nuclear instrumentation requind vill have been installed and checked out.
(2) Control rod configuration for criticality vill have been estimated.
(3) startup rates vill not exceed one decade per minute.
(4) One control rod group vill be cocked for safety purposes.
(c) Initial core parameter u.easurements:
(1) Any plant changes which would produce a sudden lowering of reactor coolant temperature (of the order of 10 0 F) must be avoided while the reactor is approaching criticality I
or is critical. ~
t (2) Availableshutdownreactivitymustnotbereducedbelow1%K l
with a stuck control rod as determined by previous analysis and experiment. That is, the boron concentration in the system must not be reduced below the value required to give the heff of approximately .99 for the core if one control l rod should be stuck in a preset safety position vitt tL ochers inserted.
l (d) Reactor startup:
l (1) Notify all personnel that startup of the reactor plant is imminent.
1 i (2) Verify that all control rods are at the fully inserted position and then withdraw one group of control rods-to a safety position.
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(3) The following minimum startup instrument requirements must be met:
i f (1) Two source channels l
l (ii) Two intermediate range channels l
(iii) Two power range channels (4) Pressurizer heatup rate must not exceed 2500 F per hoar.
0 (5) Do not exceed 200 F differential between main coolant l
temperature and pressurizer temperature or if the differential exceeds 2000 F, do not use the pressurizer sprays.
(6) The main coolant pressure must not exceed 500 psig until the temperature of the main coolant is at least TO F.
(7) when bringing the main coolant system up to temperature and pressure, do not initiate removal of boron until main coolant l
I system temperature reaches 250 F.
(8) Verify that safety injection controller is switched to l
f aute.atic position when main coolant system pressure exceeds
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l safety injection set point pressure by 200 1.sig.
(9) when main coolant system reaches operating temperature of 0 F, start approach to criticality by intermittent program 500 rod withdrawal. The rod program vill be adjusted so as to assure that there is at least 2% shutdown upon scram with the i
most effective rod stuck.
(10) During approach to criticality, flux multiplication rates should be maintained at less than 1 decade per minute.
(e) Reactor operation:
(1) In a condition where one power range channel is inoperative, the reactor may continue to be operated at the existing power
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level provided no major rod program change is carried out and provided the power range high Icvel scram protection is set for single channel operation.
(2) Perfom periodic calorimetric deterr.inations for both primary and secondary systems and adjust nuclear power channels if necessery.
(3) Prmptly acknowledge all annunciator alams and correct abnomal conditions as soon as possible.
(4) If the nomal or emergency power cupply is lost, shut down the reactor until such time as both power supplies are in service.
(5) Waste disposal storage tanks should be arranged to receive water ejected frcen the main coolant system.
(6) Monitor the neutron flux level instruments as the station load is changed. ~
(T) When the reactor is. critical at zero power level or when the load isbeing reducal to zero power level, adjust seemdary steam pressure to maintain the main coolant system above h30 F.
4 (f) Reactor hot shutdown:
(,' ) One control rod group vill be left in a cocked position so that the reactor ic suberitical by at least 1% k.
(2) The main coolant system vill be maintained at operating temperature and pressure by means of unin coolant pump heat, residual htat in core, pressurizer heaters, and discharge of steam to 2cain steem header, (g) Reactor cold shuMovn:
(1) One contro.'. rod grotp vill be left in a cocked position so L,
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, that the reactor is suberitical by at least 1% k prior to reducing the temperature and pressure.
(2) The cooldown rate vill not exceed 2000 F per hour.
(3) When the main coolant temperature reaches 430 F, inject a sufficient saount of concentrated boric acid to make the mactor suberitical by at least 5% k at ambient tempe:ature with all rods inserted in the com. After a suitable =4rina time has elapsed, the boron content of the main coolant vill
. be determined by samplin6+
L (4) The " low main coolant pressure" s: ram override vill be r
. initiated prior to reducing the main coolant pressure.
(5) The safety injection control switch will be placed on manual when the pressure reaches approximately 1000 psig.
(6) The shutdown cooling system vill be put in operation when the main coolant system pressure reaches 300 F and 100 psig.
This system vill be kept in operation or operated intermittantly as needed to keep the main coolant temperature at or below 1400 F.
(h) Maintenance: .
(1) Only authorized personnel vill be allowed to enter the containment vessel to perform inspections and maintenance work. During operation at power or when the reactor is at operating temperature and pressure, at least two men vill be sent into the containment vessel whenever it is-necessary co make inspections or perform minor repairs. Minor repairs will consist of instrument and equipment adjustments that can be made vith amall hand tools.
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21 (2) The various areas of the plant and campartments in the containment vessel vill be monitored for radiation and contamination pr or to carrying out maintenance work.
(3) Lines and systems vill be sampled for radioactive gases prior to being opened up for maintenance.
(4) Special clothing vill be provided for maintenance work to prevcnt or restrict the spreading of radioactive contamination.
Other protective equipent such as filter type breathing apparatus vill also be available.
(5) In the case of maintenance jobs performed under radiation exposure conditions which limit the working period, special.
check lists and procedures vill be developed and the personnel ,
involved vill be thoroughly briefed prior to entry into the work area.
(6) The air lock vill be used far personnel access- to the containment vessel at all times, except W en loading a complete new core or when the head is on the reactor and the main coolant pressure and temperature are less than 300 psig and 200 0 F, respectively, andthereactorissuberiticalbyatleast3%.
(7) The equipent access opening vill be used only when the reactor vessel head is off and the core is suberitical by at least 10% or when the head is on the reactor vessel and the main coolant pressure and temperature are less than 300 psis and 2000 F, respectively, and the reactor is suberitical by at least10%.
(1) Refueling and Control Rod Replacement:
(1) Items (1), (2), (3), and (h) under 12(a) - Initlal core Loading, vill be complied with during refueling.
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(2) In the et je of the removal of an individual control rod, the four adjacent fuel assemblies will be removed first.
(3) A minimum of two source range flux channels and two inter.
mediate flux channels vill be in service during these oper-ations.
(h) Radiation monitoring equipment and alams vill be in service during these operations.
(j) Emergencies:
(1) In case of high radioactivity level'in the containment vessel indicated by either the air particle detector alarm or radio-active gas detector alarm, the reactor vill be shut down. -- The purge system vill be put into operation if the stack discharge activity does not exceed 2 x 10~I ue/cc. If this action does not redace the radioactivity level,-a 2wactor cooldown vill be initiated.
(2) If the stack radioactivity alam is actuated the various possible sources of radioactivity will be shut off sequentially.
If this; action does not remedy the condition, the reactor vill-be shut down or cooled down as the case may be. ,
(3) If the steam generator blowdown radioactivity alam -is actuated, the blevdown vill be discontinued imanediately and the reactor vill be shut down.
-(4) If the radioactive alarm in -the liquid effluent line to the river is actuated, the valve in this line vill be closed immediately.
.(5) In.caseofhighcoolantradioactivityabove20uc/ce,.~the purification system flow will be increased and if this does not help to' reduce the radioactivity in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor-vill be shut down.
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.. . ( . J (6) Operating instructions vill be prepared for emergencies '
such as loss of coolant, loss of coolant flow, control rod malfunction, loss of steam load, failum of reactor control circuit, and uncontrolled heat extraction vill enumerate the automatic actions that should take place and also list the immediate manual actions that the operator should take. In all of these emergencies, if the automatic control does not 4
shut down the reactor, the operator is instructed to shut the reactor down by either manual scram or by runna6 in the control rods.
4 13 Provisions have been made to test the major safety systems and controls.
These systems and controls vill be tested in accordance with the following schedule,
~ i Safety Injection Pumps and Autcmatic Startup Control Monthly Radiation Monitor Circuita Monthly Control Rod Drive Scram Speed Every 3 months Scram Settings Everc 6 months Scram Circuit Response Time Measurement Every 6 months
- 14. The No. 2 turbine has a manual trip and an overspeed' trip. The manual trip is nomally used enry time the turbine is shut down and the over-speed trip vill be checked at least every six months.
- 15. A containment vessel pressure alarm set for 5 psig vill be provided in the main control room. Motor operated or pneumatically operated i
valves in outgoing lines from the containment vessel can be closed remotely from the main control room. <
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- 16. Tne steam generator blowdown radioactivity alarm point will be set for 2 x 10-b ue/cc.
- 17. Calculated boron concentrations for various reactor operating conditions are as follows:
Condition ppm Cold - 10% suberitical with all rods inserted in core 1500 Critical at zero power less than 200 Full power less than 10
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0 SAXTON NUCLEAR EXPERIMENTAL CORPORATION PROPOSED DEFINITION OF " FACILITY" FOR INCLUSION IN OPERATING LICENSE This license applies to the Saxton Nuclear Experimental Corporation nuclear facility located in the Borough of Saxton in Liberty Township, Bedford County, Pennsylvania. As used in this license the tem " facility" means:
- 1. The containment vessel which houses the reactor, stesn generator, main coolant system, other miscellaneous auxiliary systems, and the fuel storn6e vell.
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- 2. The reactor core including the control rods, control i
rod drives, support structure, and r.ormal operation instrumentation and controls.
3 The main coolant loop includin6 the piping, steam generator, main coolant pump, reactor vessel, and normal operation instrumentation and controls.
- 4. The pressure control and relief system vhich consists of a pressurizer, discharge tank, relief valve, safety valves, electric heaters, and i' - rumentation and controls.
5 The charging system consisting of hi6h pressure pumps and instruments and controls.
- 6. The purification system consisting of heat exchangers, flow coritrol valve, demineralizers, and instrumentation and controla.
1 7 The chemical addition system consisting of a steam heated boric acid tank, boric acid pump, and a chemical addition tank.
- 8. The campling nud lead detection system consisting of high pressure and low pressure sampling and leak detection lines, sample coolers, sample bcunbs, and instnanents and controls.
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9 The shutdown cooling system consisting of a low pressure heat exchanger, pumps' and instrumentation and controls.
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- 10. The safety injection system censisting of two high pressure pumps arranged in series, a high pressure and icy pressure piping system, and instrumentation and controls.
- 11. The station service electrical system consisting of a normal and emergency power supply, 440-volt feeder busses, pressurizer heater control center, motor control centers, battery and battery charger, safeky injection punpa supply, inverter bus and vital bus supply, and main coolant pump supplies.
- 12. The radioactive vaste disposal facility consisting of a solid vaste dispocal system, a liquid vaste disposal system, and a gaseous vaste disposal system.
13 The radia;,1on monitoring system consisting of plant process monitoring, plant effluents monitoring, site monitor'ing and plant area monitoring.
- 14. Shielding inside and immediately outside the containnsnt vessel, in the valls of and inside the containment vessel, in the valls
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of and inside of the control and auxiliary building, and in the vaste t natment building.
15 The fuel han m ns system consisting of special tools, hoists, and fuel storage rack.
- 16. The secondary coelant system inside the containment vessel and the piping outside the containment yessel up to the feed water regulat'ing valve and the steam pressure regulating valve.
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