ML19345A650
| ML19345A650 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/30/1964 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19345A648 | List: |
| References | |
| NUDOCS 8011240432 | |
| Download: ML19345A650 (10) | |
Text
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APPENDI X "A" YANKEE ATOMIC ELECTRIC COMPANY TEGINICAL SPECIFICATIONS APPENDED TO LICENSE NO. DPR-3 DATED JUL 0 0 US A.
SITE
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The reactor shall be located on the property ownef Fy Yankee in Rowe, Massachusetts. The site includes the property owned by Yankee and New England Power Company as shown on the map on page 300:2 of the license application.
No part of the site shall be sold or leased without the prior approval of the Commission. No structure shall be located on the site without the prior approval of the Commission except structures owned by Yankee or New England Power Company and used in their utility operation and except railroad facilities owned and used by the Hoosac Tunnel and Wilmington Railroad Company.
B.
DESIGN SPECIFICATIONS e
1.
The following sections of the license application are considered to be design specifications of the reactor and are incorporated herein in their entirety:
101 Co c Mechanical Design 201 Ma n Coolant System 202 Precsure Control and Relief System 203 Charring and Volume Control System 204 Chemical Shutdown System 210 Shutdown Cooling System 212 Safety Inj ection System 230 Reactor Vessel 2.
The pressures and temperatures used as a basis for design, materials of construction, general arrangements of the systems and their components, weights, volumes, dimensions and tolerances, methods of fabrication and applicable codes, tests and inspection procedures which appear in the following sections of the license application (excluding drawings) are considered to be design specifications of the reactor and are incorporated by reference herein:
102 Core Thermal cnd Hydraulic Design 103 Core Nuclear Design 106 Reactor Coolant Chemistry 107' Core Instrumentation
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20S Purification System 207 Corrosion Control System -- Primary Plant 209 Radioactive Waste Disposal System 213 Reactor Control System 214 Nuclear instrumentation System 21S Radiation Ebr itoring System 218 Fuel llandling System 1801124o 93 1
224 Compressed Air Systems 231 Vapor Containment 232 Radiation Shielding 23S Architectural Features Physical arrangements of structures and equipment will be as described in Section 200 of the license application. Pechanical equipment and systems will be interconnected as shown in the Fundamental Flow Diagram included in that section.
Electrical equipment and syste=s which provide station auxiliary power supply will be as described in Section 226 of the license application and will be interconnected as shown in the 2400 volt one-line diagram and the 480 volt one-line diagram, sheets 1, 2 and 3, included in that section.
The ventilation system for the control room area, radiochemical laboratory, decontamination cubicle, fuel transfer pit house, and
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I other potentially contaminated portions of the Turbine Generator, Service, Primary Auxiliary, and Waste Disposal Buildings shall be in accordance with.the description contained in Section 228 of Part B of the license application.
C.
PERFORMANCE SPECIFICATIONS Calculated values of operating variables such as pressures, temper-atures, flows, heat fluxes, reactivity coefficients and on-site radiation levels under steady state and transient conditions which are stated in the sections of the license application listed in Paragraph B, above, are considered to be performance specifications of the reactor and are incorporated by reference herein, Yankee shall not operate the facility under circumstances where there is a
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substantial variance between the foregoing performance specifications and the corresponding values determined by operation of the facility.
The performance and function of the systems described in the following sections of the. license application shall be substantially as described; however, the details of individual components and their arrangement as described in each of these sections may be altered by Yankee at its mz own discretion provided that such an alteration would not violate some other provision of these Technical Specifications:
206 Component Cooling System 208 Sampling System 211 - Vent and Drain Systen, Primary Plant 216 Vapor Container Atmosphere Control Systems 219 _ Main and Auxiliary Steam System 220 Condensate and Feed Water System 221 Circulating Water System 222' Water Supply Systen
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F a D.
OPERATING PROC 5.D.U.,RES AND. RESTRICTIONS 1:
Ogeratine Procedures The reactor shall at all times be operated in accordance with generally accepted standards of safe operating procedures and subject to the operating restrictions described in the Technical Specifi-c at ion s, All plant operations which have a significant direct or potential effect on the reactor and its auxiliary systems shall be conducted in accordance with written procedures and under the dire:t ani personal supervision of technically qualified and designateil personnel, All written operating procedures and modifications thereto shall be prepared by personnel possessing A.E.C. operators licenses who are thoroughly familiar with the reactor and its operation.
Each procedure or modification shall then be reviewed by the bbnager of Operations and appropriate staff engineers at the. Yankee central engineering office.
The Yankee Review Committee, consisting of at least 3 senior engineers and scientists employed by organizations other than Yankee, shall verify approximately every six months that an j
adequate, current and properly reviewed set of written procedures is being maintained, Normal Operation, Emergency and Maintenance Instructions sh-11 be reviewed periodically to insure that they are current and in keeping with the physical status of the plant, 2,
Cgerayng Limits 3gaglivity a,
(1)
During core loading the fuel assemblics, control rods and shim rods will be loaded one by one in water sufficiently borated to render the fully loaded core sub-critical at room temperature, by a calculated. margin of at least 7% 3 K/Ks (2)
During the refueling operation a record will be made of the neutron count rate before and after any change in core
- geometry, If a significant unexpected increase in the count rate occurs en any one channel or if an unexpected increase in the count rate by a factor of two on two of the three channels occurs after addition of a new fuel assembly or removal of a control rod, the fuel loading operat ion will be suspended until the situation can be reviewed by plant technical supervisory _ personnel.
In order to establish the shutdown margin of the core, a singin control rod will be withdrawn periodically using the manipulator crane and regulated by a plot of control rod position vs. inverse count rate multiplication.
4 Using the inverse count rate data obtained in this manner, the shutdown margin will be calculated.
If these calcu-lattens indicate that there will be less than 54 A K/K shutdown with all control rols inserted in t!.e fully loaded core, the boren concentration will be increased to provide the required 5% f5 K/K shutdown margin.
(3) At all times when the reactor is at operating temperature
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sufficient boric acid shall be present in the main coolant system so that full insertion of all centrol rods shall r=
render the reactor not less tion 4'.
[i K/K sub-critical or, if the maximum worth rod were withdrawn, not less than 2,0% 45 K/K sub-critical, (4) Sufficient bori, acid will be added to the main coolant
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system prior to cold shutdown to maintain the cold core
.x with all control rods inserted at 1 cast 5% [h K/K sub-
,,2 critical. This will be done before the teuperature 4.=g7:.:
of the main coolant system has been reduced to a point 2.,
where full insertion of all control rods would no longer render the reactor 2% 21 K/K sub-critical without the
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presence of boric acid.
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(5) The maximum reactivity insertion rate due either to withdrawal of the highest worth control rod group or to reduction of boric acid concentration in the main coolant system through dilution will not exceed 1.5 x 10'4 [s K/K per second.
(6) Whenever the reactor is shutdown, before any operation which mir.ht result in a change of reactivity, a control
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rod creap shal! be withdrawn to a height sufficient to provide a re: 0tivity worth of it for ecergency shutdown capability If for any reason this is not practical, the main coolr.nt system shall be barated to provide 5% Li K/K re cold shutdown margin with all control rods inserted.
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(7) Scurce range instrumentation shall be in service whenever the reactor is shutdows. with the count rate recorded and a startup rate alarm se: at 1 decade / minute.
At least two channels of source rar.ge instrumentation must be in
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operation and in a position to monitor the neutron population and its time variation whenever core geometry
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is being changed or if other activities are being performed
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which might increase core reactivity.
During refueling periods, one channel must be equipped with a high count rate alarm which will sound both in the control center and in the vapor container.
(S) The reactor will be scrammed automatically be:ow 15 FM clectric by a high startup rate signal set at a maximum cf 5.2 decadesf.iinutei
5 (a) The Commission shall be immediately notified should an unexplained reactivity change greater than 0.8% 6 K/K take place at any time subsequent to the first week of full power oparatien. This reporting requi rement shall be in effect only when the boron concentration in the primary system exceeds 80 ppm and within one week after a reduction to a boron concentration of less than 80 ppm.
(10)
During a reactor startup in which core reactivity or control rod pcsitions for criticality are not established, a plot of inverse multiplication rate (or count rate) versus rod position should be made, b.
Power Level (1) The steady state power level of the recctor will not exceed rated power of 600 W thermal.
(2) The reactor will be scrammed automatically by a high neutron flux level signal, set at not more than 108t, of rated power as defined in (1) above.
(3)
During operation with one loop of the four main coolant loops isolated from the system, the steady state thermal power level of the reactor will not exceed 450 W thermal.
(4)
During operation with one main coolant loop isolated, the,
reactor shall be scrammed automatically by a high neutron flux leval signal, set at not more than 108'. of the power Icvel defined in (3) above.
(5' Except for operation of the reactor at power levels not exceeding 15 W clectric, the reactor shall not be operated with less than three main coolant loops in se rvi ce.
(6) Whenevar there is a sustained outage of one of the 115 KV lines because of maintenance of fault condition, the normally open circuit breakers between the 2400 volt bus sections shall be arranged so that electrical pcwer is available to supply all safety injection pumps, The plant power level shall be reduced to a level consistent with 3 loop operation.
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(i)
At rated power the calculated heat flux at the point
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closest to burnout in the hattest channel shall not
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cy.cced 50' of the burnout heat flux as pr2dicted by the l
.Q2;' cpyrejat;cy,_ phown on page 102:19 of the license application. This ratio shall be checked escry 1000 i
equivalent full power hours of operation utilizinf, data derived f ro a the in-core inst ruraentation.
PGM M GINAL
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. (2)
'At rated power the calculated temperature of the coolant at the exit of the hottest channel shall not exceed 611
- F.
(3)
At rated power the calculated maximum clad surface temperature in the hottest channel shall not exceed 663* F.
d.
Main Coolant System (1) The reactor shall be scrammed automatically above 15 PW electric by a low main coolant pressure signal set at a minimum of 1800 psig.
(2) The reactor shall be scrammed automatically above 15 FH clectric by a low main coolant flow signal.
Low flow scram shall be initiated by low flow in not more than two of four loops for operation at or below 540 MWt.
Low flow scram shall be initiated by low flow in one of four loops above 540 FHt.
A loop lot flow condition is defined as 80% or less c' normal flow in the loop,
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(3) The reactor shall be scrammed automatically by a high pressurizer water level signal set at a maximum of 200 inches whenever the turbine generator is operating.
(4) The reactor shall not be brought to criticality at a main coolant system temperature lower than 250*F except for scheduled low power physics testing which shall be performed in accordance with written procedures.
(5)
During normal plant startup boric acid dilution shall not be commenced until the main coolant system temperature has reached equilibrium at 250*F, (6) The plant shall not be operated at loads above 15 FM electric unless the boron concentratior in the main coolant system is less than 1300 ppe.
(7) The main coolant system pressure must not exceed 500 psig until the temperature of the main coolant is at Icast 60*F above the nil ductility temperature of the reactor
- vessel, Pressures in excess of this at lew temperatures may be injurious to the reactor vessel, (S) The main coolant system heatup and cooldown rate must not exceed 50* F/hr. The pressurizer heatup and cooldown rate must not exceed 200*F/hr.
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(9) The pressurizer spray line shall not be isolated when the reactor power level is greater than 5 FM thermal.
(10) Whenever a main coolant loop is isolated from the system, it shall be borated at full ' shutdown concentrations before its temperature is reduced below 485'F.
4 (11)
An isolated main coolant loop shall be returned to service
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only after the boren concentration and the water temper-
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ature have been closely matched to existing main coolant system conditions.
An automatic valve interlock prevents any isolated loop from being returned to service if the loop temperature is more than 30*F lower than the highest cold leg temperature infthe othet loops,
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(12) The boron concentration in an isolated loop must not be g
less than that of the operating loops when the isolated 3
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loop stop valves are opened, y;ggg:
(13) When there is a substantial amount of decay heat in the
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reactor fuel, at least two main coolant loops must be
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tied to the reactor vessel (main coolant pumps may be
__g off), or the shutdown coolant system must be in operation.
For purposes of cold leak testing only, the reactor u.
1 vessel and connecting pressurizer system may be isolated from the heat removal system provided the coolant temper-sr= -
ature in the vessel does not increase at a rate exceeding 50*F per hour and thst the maximum temperature ine: case during the test period does not exceed 100*F.
e, Other Plant Protection (1) The reactor shall be scrammed autcuaticc11y, above 15 FE electric, when the turbine is tripped for any reason, i
The turbine shall be protected by all usual protective
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trips including high thrust bearing temperature, low bearing oil pressure, low condenser vacuum and overspeed.
(2). The reactor shall be scrameed automatically, above 15 FE electric when the generator is tripped for any reason.
The generator shall be protected by all usual protective trips including overcurrent, differential and loss of
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(3) The safety injection system shall be maintained in readiness to pump borated water into the reactor at all times when the. main coolant pressure is 1000 psig or higher.
A pressure switch set at not less than 800 psig main coolant-pressure shall automatically initiate operation of the
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motorized valves in this -system and a pressure swit:h set at not.lcss than 800 psig Rain coolant pressure shall
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- _ _ - =
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automatically start the high pressure safety injection pump, and a second pressure switch set at not less than n
270 psig main coolant pressure shall automatically start the low pressure safety injection pumps.
(4) The boiler feed pumps shall be automatically tripped out of service, above 15 H1 electric, by any reactor scram.
(5)
Valves in all outgoing lines from the vapor container shall close automatically if at any time vapor container pressure increases above 5 psig, (6) The integrity of the vapor container shall be maintained at all times when the reactor is critical or when the main coolant system is above 200*F or above 300 psig with the reacter core in place.
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(7) The shutdown cooling system must not be placed in operation unless the main coolant system pressure is less than 300 psig.
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At main coolant system pressures above 300 psig, the shut-down cooling system must be valved off and locked.
(2) The suction and discharge valves of the ready standby
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charging pumps shall be open during~ normal plant operation.
(9)
Ion exchangers capable of removing boron from the main
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coolant must be valved and locked closed except during scheduled boron removal operations.
(10)
At least 1500 gallons of approximately -12% by weight boric acid aqueous solution must be available in the boric acid mixing and storage tank, hot and ready for injection and,
the boric acid mixing and storage tant instrumentation and associated valves, lines and pumps shall be kept in operating condition at all times when fuel is in place and the main coolant is not borated to shutdown concen-tration.
(11)
An AEC licensed operator shall be on duty in the control room at all times when fuel is being moved or if other activities are being performed which might increase core reactivity.
At least one AEC licensed person shall be in the vicinity of the fuel handling system whenever fuel is being moved.
One AEC licensed person shall be desig-z nated as being in charge of the operation.
(12) The automatic controls associated with the reactor pro-tection system shall be maintained at the set points listed in Table 1, attached hereto, or at set points representing more conservative values of the particular
9 variables being measured.
Table I also shows the number of channels associated with each function and the number of channels normally required to initiate a scram signal:
In the et ent of a f ailure of one inst rument channel when multiple channci protection is provided for a function, the plant shall continue regular operation. The scram circuits, however, shall then operate so that activation of any of t he remaining channels for that function shall cause scram operation, except as provided in the authorization of Change No. 23.
f.
Plant Protection when the Reactor Vessel Head is Removed and the Vessel Contains Fuel (1)
All operations shall be conducted in accordance with written procedures.
(2) Before flooding the shield tank cavity with borated water, it shall be determined that the boron concentration r o.. _...
of the water in the safety injection tank is hot less
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than the boron concentration of the main coolant.
(3) The shield tank cavity water shall be sampled at 1 cast every other day and analyzed for boron concentration to assure that the minimum shutdown boron concentration is maintained, (4) The water in the reactor vessel and in the shield tank cavity shall be sufficiently borated to render the fully loaded core sub-critical at room temperature by a calcu-lated margin of at least 7% ll K/K.
(5)
An AEC licensed operator shall be on duty in the control room at all times, (6) The chemical shutdown system shall be lined up and aJail-s abic at all times to provide emergency shutdown under the '
control of the AEC licensed operator.
(7) Equipment which would make possibic inadvertent reactivity changes shall be made inoperable and tagged out of service.
(S) Manipulation of reactor vessel components or internals shall be carried out under the direct and personal super-vision of technically qualified and designated personnel.
(9)
During refueling two charging pumps and their associated valves and piping shall be available at all times to provide for addition of concentrated boric acid to the pressure
- vessel, (10)
A channel for continuous gamma monitoring shall be provided near each maniputator crane whenever spent
i-control rods or spent fuel assemblics are being handled.
(11)
Whenever a change is being made in core geometry, the equip::,ent access opening must be closed, Either the regular hatch cover or a temporary cover shall be in place, g.
1,faste Effluents (1)
Solids -- No radioactive solid wastes shall be disposed n
of at the site.
(2)
Liquids -- No radioactive liquid wastes having concen-trations in excess of those specified in Appendix B.,
Table II, 10 CFR 20, shall be discharged from the plant.
(3)
Gases -- As determined at the point of discharge from the primary vent stack and averaged over a period not exceeding one year, % concentrations of radioactive gaseous wastes discharged shall not be in excess of
- n. - w 1000 times the limits specified in Appendix B. Table II, 10 CFR 20 Any discharge to the atmosphere from the gas stripper or the combustible waste incinerator shall be
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continuously monitored at or prior to the points of such discharge. The monitor in the incinerator stack shall be kept in continuous service in order to provide an alarm and a record in the event of the release of radioactive
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gas from the waste disposal blanket gas system through the loop seal, h.
R,adplyical Health and Safyy (1)
Personnel radiation exposures'shall be maintained below the. limits established in Title 10, CFR 20, or in any
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future amendments to this regulation.
(2)
Arrangements shall be maintained with 'the Massachusetts N
State Police and with the New York Operations Office for their assistance in the event of an emergency.
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Rout _ine and Continuing Tests Routine and periodic tests shall be made at the times and in r
the manner set forth in Section 509 of the license application.
UU M a.a:T.,*' p.crF.#_'T l.i W.I PT.lY. m*f.f i.
l Ilo of Clwinels P*telred to Trip
< q ncr..w Je+t M nt Limi t s hemarkat vuur t i e.n
'istianese ras tart instrearn.Mi'*n -. - -
in ch..t artup b ate -
1 out of 2 Av.a t em S.2 dec/ min - mav
? s mr. e ran.-* chenrels a
read.or ar.an Above 1% Ne 6,grWim.c ranra c h.mn 1-i
' tis lh ?:cutron 2 out of 6 Nesne lieutron flux corresponds to Minlaum of b eperable channels Flux Level -
10&i rated power - max.
required for reactor operation 9eactor Geram lleutron Flux 1 out of 6 Ado bvpass Neutron flux decrease corresponding lavel Decrease Pelow 15 W e to 151 of 600 W t - man.
Iteactor Scram low Main Coolant 1 out of 2 Auto typass Ith) psig - min.
Pressure -
fielow 15 PSe Reactor Scram Lou Main Coolant No more than Auto bypass 005 of normal main coolant Flow -
2 out of b Below 15 W e flow in any leop - min.
Weactor scram below 540 M=t
.1 out of h above SLO Pldt
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High Pressuriser 1 out of 1 Manual 2m inches - max.
In service whenever turbine bater Level -'
generater is operating.
Reactor t cram Manual -
Not Arplicable Mone Avellable any time Reactor Scram Turbine Trip -
Ifot Applicable Aute bypass lisual Turbine Trip set points Turbine trip scrams reatter and g.
Neactor Scram Pelow IS We trips renerator aeove 15 m g siener ator Trip -
Not Applicable Auto bypass t'sual "senerator Trip set points Ganarator trip scrams reactor arwl f3/
licactor Scram I -Inw 15 P%e trips turbine ahnve 15 PLe
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- it.can Generater h out of b Nece Not l#wer then 15 inches below Coincident low mat *r level t rips XT[
Low Water Level normal water level turbine throttle valves. Turbtne Trip trip serans reacter above 15 PW k
Manual thrbine Not applicable A4to bypass Available any time above 15 Ne
- wherator Trip -
P* law 15 !%e H*act or, crape
,,.h SJety injection 1 out of I h uel
&lo pstr. main conlant ;ressure-min iaartnr n..rmal operation sys en is c
Operation (voterited valves e,d high g ressure set for automatic initiatl.a.
E rump operate)
V ety inj-etion may te initiated pgj 270 psig main enolant pressure-min manually at any time 7ggy -
(Iow pressure pumps start)
Pressuriser Not Applicable None 21.85 psig. FO. I valve - man
.,at ety val ve -
290 psir, No. 2 valve - max.
upcration WN
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? yer Contai n. r 1 eut f2 1 te-
- $ psic vap r egn'.a tner pres uee =an Clases t rip valv. s in snit #%in e e
ut <cint Lisw Trip -
11ers in valver e<n:ain r Valv. Operation Main Celent valve Pot A +1trable N ne.
3[F trwerature differe.tial - max Preven's any i solate-1 1 o f r a irt-rlock twine placad into aparation if t he 1 sop ems.erature is enr.
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