ML19339A770
| ML19339A770 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/23/1961 |
| From: | Kirk R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19339A769 | List: |
| References | |
| NUDOCS 8011040757 | |
| Download: ML19339A770 (14) | |
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UNITED STATES Sh ATOMIC ENERGY COMMISSION
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WASHINGTON 25, D. C.
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nara YANKEE ATomC ELECTRIC COMPANY DOC ET NO. 50-29 L 1 C, y E S,,3 License No. DPR-3 Amend.,ent No. 3 Issued 1.
This license applies to the pressurized water reactor (hereinafter referred to as the " reactor") which is owned by Yankee Atomic Electric Company (hereinsfter referred to as " Yankee"), located in Rowe, Massachusetts, and described in the technical specifications attached as Appendix A hereto.
2 Subject to the conditions and recuirements incorporated herein, the Commission hereby licenses Yankee:
A.
Pursuant to section 10h(b) of the Atomic Energy Act of 195h, as amended, (hereinafter referred to as the "Act") and Title 10 CFR, Chapter 1, Part 50, " Licensing of Production and Utilization Facilities" to possess and use the reactor as a utilization facility; B.
Pursuant to the Act and Title 10 CFR, Chapter 1, Part 70, "Special Nuclear Material", to receive, possess and use 2300 kilograms of contained uranium 235 as fuel for the operaticn of the reactor; and.
C.
Pursuant to the Act and Title 10 CFR, Chapter 1, Part 30, " Licensing of By-product Material", to possess, but not to separate, such by-product material as may be produced by operation of the reactor.
3.
This license shall be deemed to contain and be subject to the conditions specified in section 50.5h of Part 50 and section 70.32 of Part 70; is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A.
Technical Specifications:
1 The technical specifications attached as Appendix A hereto are in'-
corporated as terms of this license. Yankee shall operate the reactor only in accordance with the technical specifications. No changes shall it be made 'in the techr'al specifications unless authorized by the Com-mission.
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2.
If Yankee shall desire to make any change in the reactor or in its operations requiring a change in the technical specificatione, Yankee shall subnit a written recaest for authorization, accompanied by an cppropriate hazards analysis with aspect thereto.
a.
If the' Director, Division of Licensing and Regulation of this Connission, determines that the proposed change presents significant hazards considerations not described or implicit in the license application as amended as of the date hereof, he shall refer the request to the Advisory Committee on Reac-tor Safeguards and shall order a public hearing in accordance with applicable procedures. Yankee shall be notified promptly of a decision to refer a request to the Advisory Committee on P.cactor St.feguards or to public hearing.
b.
If the Director, Division of Licensing and Regulation of this Commission, determines that the proposed change does not present significant hazards considerations not described or implicit in the license application as amended as of the date hereof, he may authorize the change upon finding tha+ there is reasonable assurance that the health and safety of the public will not be endangered. A copy of the authorization must, be filed in the record of this proceeding.
r c.
The Director, Division of Licensing and Regulation of this Con =ission, shall refer to the Advisory Committee on Reactor Safeguards and to public hearing any request by Yankee to operate L
the reactor at a steady state power level in excess of h85 V4 (thermal).
B.
Records In addition to those otherwise required under this license and ap-plicable regulations, Yankee shall keep the following records:
(1) Reactor operating records, including pcwer levels and periods of operation at each power level.
(2)
Records showing the radioactivity released or discharged into
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the air or water beyond the effective control of Yankee as measured at or prior to the point of such release or discharge.
l (3) Records of radioactivity levels on site and at off-site moni-toring stations.
(h) Records of scrams, including reasons therefor.
(5) Records of reactor tests and measurements perfomed pursuant to the requirements of the technical specifications.
(6)
Records of maintenance operations involving substitution or replacement of reactor equipment cr components.
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Records of changes mads in ths systems list:d in paragraphs (7)
"B" and "C" of the technical specifications and thn reasons
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therefor.
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y C.
Reports In addition to those otherwise required under this license and ap--
plicable regulations, Yankee shall make the following reports:
Yankee shall make an im:=diate report of any indication or (1) occurrence of a pessible unsa'fe condition relating to the operation of the reactor, including, without implied limita-(a) any accidental release of radioactivity, whether tions or not resulting in personal injury or property damage or _
exposure above permissible' limits; and (b) any subs,tantial s
variance disclosed by aperation of the reactor from the per-formarne specificatiens set forth in the technical specifi-Cations.
2 Within 20 days following the end of each calendar month, (2)
Yankee shall submit an operation report for such month sum-marizing data with respect to the following:
(a) Hours use of the reactor.
1 (b)
The electric output of the plant.
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(c) Shutdowns of the reactor, with a brief explanation of the cause and duration of each shutdown.
(d) Levels of radioactivity recorded at the site and at off-site monitoring stations.
(e) Levels of radioactivity in principal systems established by chemical analysis.
(f) Routine releases, discharges and shipments of radioactive materials.
(g) ' Principal maintenance performed and principal changes made in the reactor and associated systems with the reasons therefor.
(h) Significant changes made in operating procedures or in plant organization.
(i) A description of significant tests performed during the
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month and the results of any test analyses completed dur-ing the month. The tests reported shall include periodic determinations of the effects of plutonium buildup on re-activity coefficients and cf reactor pcuer distribution as measured by use of the in-core instrumentation.
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(j) Significant changes or new information regarding
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transient or accident analyses.
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(k") A description of any other significant or unusual occurrence or operating condition experienced during the
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month.
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(3) On er before December 31, 1961, Yankee shall submit a report describing the results of the use of the continucus vapor con-
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l tainer leakage monitoring system in determining the vapor con--
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tainer leakage rate.
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l (h) Within 90 days following the end of each calendar yet.r, Yankee shall submit a financial report for such year, including.
4 a balance sheet at the end of such year and a statement of x..
income and surplus for such year; and.a sumary of the amount
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and type of financial protection in effect at the end of such p
year pursuant to section 170 of the Act.
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!:..s Each such report shall be in writing, signed by a responsible offi-ry
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cer of Yankee and shall be addressed to the Cc=ission, Attention.
Division of Licensing and Regulation. 25 copies of each report
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shall be submitted. Reports submitted pursuant to (1) above may JE E
be made initially by telephone, telegram or orally but shall be h
confirmed in writing promptly thereafter.
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D.
Amendments to the license application i
Yankee may submit amendments to its license application at any time or frca time to time, but no such amendnent to the license application shall be effective to change or modify the technical specifications unless authorized by the Commission in accordance with the procedures set fcrth in paragraph 3.A.
h.
Pursuant to section 50.60 of the Regulations, Part 10 CFR, Chapter 1, Part 50, the Commission has allocated to Yankee for use in the operation
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of the reactor 6,002.6 kilograms of uranium 235 contained in uranium F
at the isotopic ratios specified in Yankee's license application. Esti-nated schedules of special nuclear material' transfers to Yankee and returns to the Commission are contained in Appendix B which is attached hereto. Shipments by the Commission to Yankee in accordance with Column (2) in Appendix B will be conditioned upon Yankee's return to the Commission of material substantially in accordance with Column (3) of Appendix B.
5.
This license is effective as of the date.of issuance and shall exoire November h, 1997.
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':*:h FOR TrE ATOMIC ENERGY ConIISSION
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Attach.ents:
De';It.t/ Director Appendix A Division of Licensing and Regulation Appendix B 2 3 1961
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t APPE'IDII "A"
,.g YANKEE ATOMIC ELECTRIC COMPANY
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Technical Specifications
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A.
SITE
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ine reactor shall be located on the property owned by Yankee in Rowe, Mass.
The site includes the property owned by Yankee and New England Power Company as she en 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
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approval of the Commission except structures owned by Yankee or New England Power Company and used in their utility operation and except railroad facilities p:
owned and used by the Hoosac Tunnel and Wilmington Railroad Company.
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B.
DESIGN SPECIFICATIONS i
i 1.
The following sections of the license application are considered to be design specifications of the reactor and are incorporated herein in E..,
their nntirety:
+i 101 Core Mechanical Design 201 Main Coolant System h.
202 Pressure Control and Relief System 203 Charging and Volume Control System il fi 20h Chemical Shutdown System
[9" 210 Shutdown Cooling System 212 Safety Injection System 230 Reactor Vessel i
2 The pressures and temperatures used as a basis for design, materials of I
construction, general arrcngements of the systens and their components, weights, volumes, dimensicas and tolerances, methods of fabrication and
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applicable codes, tests and inspection procedures which appear in the following sections of the license application (excluding drawings) are i
considered to be design specifications of the reactor and are incorpor-U ated by reference herein:
102. Core Thermal and Hydraulic Design 103 Core Nuclear Design 106 Reactor Coolant Chemistry F
107 Core Instrumentation 205 Purification System 207 Corrosion Control System--Primary Plant 209 Radioactive Waste Disposal System 213 Reactor Centrol System 21h Nuclear Instrumentation System 215 Radiation Monitoring System 218 Fuel. Handling System 22h Compressed Air Systems 231 Vapor Containment 232 Radiation Shielding 235 Architectural Features I.
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p Physical arrangements of structures and equipment will be as described in Section 200 of the License Application. Mechanical equipment and systems will be interconnected as shown in the Fundamental Flow Diagram included I
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- in that section.
Electrical equipment and systems which provide station auxiliary power supply will be as described in Section 226 of the License Application and will be interconn,ected 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 other potentially F
contaminated portions of the Turbine Generator, Service, Primary Auxiliary,'
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and Waste Disposal Buildings shall be in accordance with the description contained in Section 228 of Part B of the license application.
V C.
PERFORMAPCE SPECIFICATIONS Calculated values of operating variables such as pr'essures, temperatures, flows,
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heat fluxes, reactivity ccefficients and on-site radiation levels under steady state and transient conditions which are stated in the sections of the License
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Application listed in Paragraph B, above, are considered to be performance H
specifications of the reactor and are incorporated by reference herein. Yankee b-shall not operate the facility under circumstances where there.is a substantial variance between the foregoing performance specifications and the corresponding
_}i values determined by operation of the facility.
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The performance and function of tihe systems described in the following sections of the License Application shall be substantially as described; however, the t
details of individual components and their arrangement'as described in each of these sections may be' altered by Yankee at its own discretion provided that such an alteration would not violate some other provi_sion of these Technical Specifica-tions.
206 Component Cooling System 208 Sampling System 211 Vent and Drain System, Primary Plant t
216 Vapor Container Atmosphere Control Systems y
219 Main and Auxiliary Steam System 220 Condensate and Feed Water Systems-221 Circulating Water. System 222 Water Supply System D.
OPERATING PROCEDURES AND RESTRICTIONS 1.
Operatino Procedures The reactor will at all times be operated in accordance with generally
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accepted standarus of safe operating procedure, subject to the operating-restrictions set forth below. 'All cperations will be conducted in accord-ance with written procedures and under the direct and personal supervision of technically qualified and designated personnel.
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m-The Objectives, Conditions and Precautions set forth in the individual instructions contained in the following,. sections of the License Applic3-k tion wi'11 be observed:
504 Normal Plant Operation Instructions 505 Emergency Instructions 506 Plant Maintenance Instructions
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2.
Ooeratino Limits a.
Reactivity b
(1) During core loading the fuel assemblies, control rods,and shim b rodswill)beloadedonebyoneinwatersufficientlyborated
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to rende~r the fully loaded core at least 5% d K/K'sub-critical 9
at room temperature.
(2) During core loading a plot of inverse source multiplication or M
inverst.: count rate against number of fuel assemblies in the cor6 will be made as loading progresses.
If at any point in
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the loading procedure, projection of the plot indicates that
=i criticality might occur if the number of fuel assemblies then
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in the core were doubled the boron concentration will be in-F "
creased sufficiently to correct this condition before additional g
fuel assemblies are inserted.
(3) At all times when the reactor is at operating temperature full insertion of all control rods shall render the reactor not less than 3% d K/K sub-critical without boric acid in the main coolant system.
(4) Sufficient boric acid will be added to the main coolant system prior to cold shutdown to maintain the cold core with all con-trol. rods inserted at least 5% A K/K sub-critical. This will be done before the temperature of the main coolant system has been reduced to a point where full insertion of all control rods would no longer render the reactor 2% dK/K sub-critical without the presence of boric acid.
(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 d K/K per second.
(6) Whenever the reactor is shut down, before any operation which might result in a change of reactivity, a control rod group shall be withdrawn to a height sufficient to provide a reactivity worth of 1% for emergency shutdown capability.
If for any reason
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this is not practical the main coolant system shall be borated to provide 5% dK/K cold shutdown margin with all control rods inserted.
(7) The reactor will be scrammed automatically below 15 !.T electric
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by a high startup rate-signal set at a maximum of 5.2' decades /
minute.
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, ewe.r Level p
4 (1) The steady state power level of'the reactor.will not exceed E
rated power of 485 IM thermal.
(2) The reactor will be scrammed automatically by a high neutror) p flux level signal, set at not more than 120% of rated power as defined in (1) above.
h; (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 90% of rated power as defined in (1) above.
y (4) Durir.g operation with one main coolant loop isolated the reactor will be scrammed' automatically by a high neutron flux level signal, set at not more than 110% of rated power as defined in ~
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(1)above.
(5) EEcept for operation of the reactor at power levels not exceed-ing 15 MW electric, the reactor shall not be operated with loss than three main coolant loops in service.
c.
Thermal (1) At rated power the calculated heat flux at the point closest to burnout in the hottest channel shall not exceed 50% of the burn-out heat flux as predicted by the Bettis Correlations, referenced
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on page 102:1 of the License Application. This ratio shall be checked every 1000 equivalent full power hours of operation utiliz-ing data dervied from the in-core instrumentation.
(2) At rated power the calculated temperature of the coolant at the exit of the hottest channel shall not exceed 603 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 will be scrammed automatically above 15 FM electric N
by a low main coolant pressure signal, set at a minimum of 1800 psig.
l (2) The reactor will be scrammed automatically above 15 FM electric by a_ low main coolant' flow signal, set at a minimum of 60% of normal main coolant flow..
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(3) The reactor will be scrammed automatically by'a high pressurizer water level signal set at a maximum of 275 inches whenever the turbine generator is operating.
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i (h) The reactor will not be brour,ht to criticality at a main coolant 0
system temperature lower than 250 F except for scheduled low power physics testing which will be performed in accordance with written procedures.
(5) During normal plant startup boric acid dilution will not be com-
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mcnced until the main coolant system temperature has reached ecuilibrium at 2500 F.
(6) The plant will not be operated at loads above 15 Y/ electric h[
unless the borcn concentration in the main coolant system is less than 80 ppm. The plant will not be operated below 15 MW electric
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with more than 220 ppm of. boron in the main coolant system except
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during normal startups or during low power physics testing which will be performed in accordance with written procedures.
R (7) Whenever a main coolant loop is isolated from the system it will be borated at full shutdown concentrations before its temperature is reduced below hB5 F.
(8) An isolated main coolant loop will be returned to serviced only after the boron concentration and the water temperature have been i=r-closely matched to existing main coolant system conditions. An 6,
automatic valve interlock prevents any isolated loop from being u
returned to service if the loop temperature is more than 300 F is lower than the highest cold leg temperature in the other loops.
hp e.
Other Plant Protection (1) The reactor will be scrammed automatically, above 15 MN electric, when the turbine is tripped for any reason. The turbine will be F
s protected by all usual protective trips including high thrust bearing temperature, low bearing oil pressure, low condenser vacuum and overspeed.
(2) The reactor will be scranmed automatically,' above 15 MN electric, when the generator is tripped for any reason. The generator will be pro-tected by all usual protective trips including overcurrent, differential and loss of field.
(1) The safety injection system will be maintained in readiness to pump borated water into the reactor at all times when the main coolant r-pressure is 1000 psig or higher. A pressure switch set at not less than 800 psig main coolant pressure will automatically initiate operation of the motorized valves in this system and a pressure switch set at not less than 270 psig main coolant pressure will autcmatically start the safety injection pumps.
(h) Effective August 1,1961, the boiler feed pumps will be autenatically
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tripped out of service, above 15 M4 electric, by any reactor scram.
(5) Valves in all outgoing lines from the vapor container will close automatically if at any tine vapor container pressure increase above 5 psig.
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G 6-(6) The integrity of the vapor container will be maintained at all times when the reactor is critical or when the main coolant il 0
system is above 200 F or above 300 psig with the reactor core in place.
(7) The automatic controls associated with the reactor protection system will be maintained at the set points listed in Table I, attached hereto, or at set points representing more conservative values of the particular 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 event of failure of one instrument channel when*
multiple channel protection is provided for a function, the plant g
will continue regular operation.- The scram circuits, however, g
will then operate so that activation of any of the remaining h
channels for that function will cause scram operation.
6 f.
Plant Protection when the Reactor Vessel Head
,is Removed and the Vessel Contains Fuel.
55 (1) All operations will be conducted in accordance with written pro-cedures.
(2) The water in t.he reactor vessel and in the shield tank cavity will be sufficiently borated to render the core at least 5% A K/K sub-critical at room temperature.
(3) Normal plant source range instrumentation will be in service at all times with the count rate recorded and a startup rate alarm set at I decade / minute.
(4) An AEC licensed operator will be on duty in the control room at all times.
(5) The chemical shutdown system will be lined up and available at all times to provide emergency shutdown under the control of the AEC licensed operator.
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(6) Equipment which would make possible inadvertent reactivity changes will be made inoperable and tagged out of service.
L (7) Manipulation of reactor vessel components or internals will be carried out under the direct and personal supervision of techni-cally qualified and designated personnel.
g.
Waste Effluents (1) Solids -- No radioactive solid wastes will be disposed of at the site.
(2) Liquids -- No radioactive liquid wastes having concentrations in excess of those specified in Appendix B., Table II,10 CFR 20, will be discharged from the plant.
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(3) Gases -- As determined at the point of discharge from the primary vent stack and averaged over a period not exceeding one year, the concentrations of radioactive gaseous wastes dis-charged shall not be in excess of 1,000 times the limits speci-fled in Appendix B, Table II, 10 CFR 20.
Any discharge to the atmosphere from the gas stripper or the combustible waste inc'in-erator shall be continuously monitored at or prior to the point of such discharge. The monitor in the incinerator stack shall be kept in continuous service 'n order to provide an alarm and a record in the event of the release of radioactive gas from the waste disposal blanket gas system through the loop seal.
h.
Radiolecical Health and safetv Personnel radiation exposures will be maintained below the limits established in Title 10, CFR 20, or in any future amendments to this regulation.
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Routine and Continuino Tests is h
Routine and periodic tests will be made at the times and in the manner set forth in Section 509 of the License Application.
i I
..,J Att.
i TARIE T RE ACTOR PROTfCTION_ SET POINTS r.
p No. of Channels l
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Tucctier.
Raouired to Trip Bypasses Set point Limits Remarks:
$g liigh Startup Rate -
1 out of 2 Auto bypass S.2 dec/ min - max 1 Reactor Scram Above 15 MWe "igh Neutron 2 out of 3 None Neutron flux corresponds to Pinimum of 2 operable channels Flux Level -
120% rated power - max required for reactor operation.
Reactor Scram Low Main Coolant 1 out of 2 Auto bypass 1800 psig - min l
Pressu:e -
Below 15 MWe i
Reactor Scram 1
Los Eais Coolant 2 out of 4 Auto bypass 60% of normal main coolant Flen -
Below 15 MWe flow - min Reactor Scram i High Pressurizer 1 out of 1 Manual 275 inches - max In service whenever turbine generator is operating.
7ater Level -
Reactor Scram Panual -
'Not App!! cable None Available any time Reactor Scram Turbine Trip -
Not Applicable Auto bypass Usual Turbine Trip set points Turbine trip scrams reactor and Re ctor Scram Below 15 MWe trips generator above 15 M'e.
Generator Trip -
Not Applicable Auto bypass Usual Generator Trip set points Generator trip scrams react'or and Reactor Scram Delow 15 MWe trips turbine above 15 MWe.
Manual Turbine Not Applicable Auto bypass Available any time above 15 MWe Generator Trip -
Below'IS MWe Reactor Scram Safety Injection 1 out of 1 Manual 800 psig main coolant pressure-min During normal operation system is I( Operation (motorized valves operate) set for automatic initiation.
t 270 psig main coolant pressure-min Safety injection may be initiated f
(pumps start) manually at any time.
I3 Pressurizer Not Applicable None 2485 psig, No. 1 Valve - max 4 Safety Valve 2560 psiq, No. 2 Valve - max lCperation Vapor sontainer 1 out of 2 None 5 psig vapor container pressure-max Closes trip valves in outgoing lines in vapor container.
Outgoing Line Trip - '
Valve Operation Main Coolant Valve Not Applicable None 30 F temperature differential - max Prevents any isolated loop from being placed into operation if the, Interlock loop temperature is more than 30 F lower than highest cold leg t'emper-ature in the remaining Icops.
botes Reactor scram always initiates turbine and generator trip.
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1-APPENDII B lp.
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DMuted Schedule of Trancfors of Specini Moelear Material fre.1 % centssion to Ed:ce and to the Ce:. mission fron Yankeot (1)
(2)
(3)
(h)
(5)
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Not Yearly Cumulative Distribution Distribution Date of Transfers Including Inciuding Transfer trc:s AEC Returns by Yankee Cur.uiative Cumulative (Fiscal toYankee(a) to A s (b)
~,osses Losses Year)
Kgs.U-235 Kgs.'U-235 Egs.U-235 Egs. U-235 208.8 208.8 1959 208.8 590.2 799.c 1960 590.2 719.1 1,518.1 1961 719 1 1962 803.1 6232(c) 179 9 1,698.0 5h5.9
( 51i5.9 )
1,152.1 1963 196h 81h.3 622.8 191.5 1,3h3.6 1
815.0 2,158.6 1965 (15 0 622.8 (622.8) 1,535.8 1966 1967 815.0 622.8 192.2 1,726.0 815.0 2,5h3 0 1968 815 0 622.8 (622.8) 1,920.2 1969 1970 815.0 622.8 192.2 2,112.h 815.0 2,927.h 1971 815.0 622.8 (622,.8) 2,30h.6 1972 1973 815.0 622.8 192.2 2,b96.8 815.0 3,311.8 197h 815.0 h.
622.8
('622.8) 2,698.0 1.75 1976 815.0 622.8 192.2 2,861.2 815.0 3,696.2 1977 815.0 622.8 (622.8) 3,073.h 1978 1979 815.0 622.8 192.2 3,265.6 815.0 h,oSo.6 1980 815.0 622.8 (622.0) 3,h57.8 1981 1982 815.0 622.8 192.2 3,650.0 815.0 h,h65.0 1983 815.0 622.8 (622.8) 3,8h2.2 198h 1985 815.0 622.8 192.2 h,03h.h (Continued)
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(2)
(3)
(h)
(g) 1986 815.0 815.0 h, Bhp.h 1987 622.8 (622.8) h 226.6 1988 815.0 622.8 192.2 h,418.8 1989 815.0 815.0-5,233.8 1990 622.8 (622.8) hh,,611.0 1991 815.0 622.8 192.2 803.2 1992 815.0 815.0 5,618.2 1993 622.8 (622.8)~
h,995.h 199h 815.0 622.8 192.2 5,187.6 1995 815.0 4
815.0 6,002.6 1996 622.8 (622.8) 5,379.B 1997 815.0 622.8 192'.2 5 572.0 1998 622.8 (622.8) h,9h9.2 1999 61.2 *(a)
_ ( 61.2) h,888.0 **
21,065.5 16,177.$
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(c 3.h5 U-235 (b
2.655 U-235
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3.025% b-23$(Hot Fuel) except (c) and (a)
(c (HotFuel)
- Inve.ntory to be returned
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- Fabricatica and burnup losses
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