ML19339B985
| ML19339B985 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/11/1962 |
| From: | Lowenstein R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19339B983 | List: |
| References | |
| NUDOCS 8011110572 | |
| Download: ML19339B985 (16) | |
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YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO. 50-29 LICENSE
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License No. DPR-3 Amendment No. 4 This license applies to the pressurized water reactor (hereinafter 1.
referred to as the " reactor") which is owned by Yankee Atomic Electric Company (hereinafter 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 requirements incorporated herein, the Commission hereby licen,ses Yankee:
A.
Pursuant to section 104(b) of the Atomic Energy Act of 1954, 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 i.
contained uranium 235 as fuel for the operation of the reactor; f
i and j:
p 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 50.54 of Part 50 and section 70.32 of Part 70 of 8011110 f72
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, the Regulations, Title 10 CFR, Chapter 1; is subject to all appli-
.m cable 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 The technical specifications contained in Appendix A hereto (here-inafter referred to as technical specifications) are hereby incorporated in this license. Except as provided in Section 50.59 of the Commission's regulations, Yankee shall operate the facility in accordance with the technical specifications.
B.
Authorization of Changes, Tests and Experiments Yankee may (1) make changes in the facility as described in the hazards summary report, (2) make changes in the procedures as described in the hazards summary report, and (3) conduct tests or experiments not described in the F 4zards summary report, only in accordance with the provisions of Section 50.59 of the Commission's regulations. As used in this license, the term
" hazards summary report" means Part 2 of the license application as amended as of the date hereof and as may be further amended from time to time in accordance with the procedures of paragraph 3.E.
of this license.
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C.
Records in addition to those othe rwise required under this license and applicable regulations, Yankee shall keep the following records:
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(1) Reactor operating records, including power levels and periods of operation at each power level.
Records showing the radioactivity released or discharged (2) into the air or water beyond the effective control of
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Yankee as measured at or prior to the point ef such release or discharge.
i Records of radioactivity levels on-site and at off-site (3) e monitoring stations.
(4) Records of scrams, including reasons therefor.
Records of reactor tests and measurements performed (5) pursuant to the requirements of the technical speci-fications.
Records of maintenance operations involving substitution (6) or replacement of reactor equipment or components.
t (7)
Records of changes made in the systems listed in para-i graphs "B" and "C" of the technica1 specifications and
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the reasons therefor.
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D.
Reports In addition to those otherwise, required under this license and applicable regulations, Yankee shall make the following reports:
Yankee shall make an immediate report of any indication (1) or occurrence of a possible unsafe condition relating to the operation of the reactor, including, without implied limitation:
(a) any accidental release of radioactivity, whether or not resulting in personal i-J
4 injury or property damage or exposure above permissible limits; and (b) any substantial variance disclosed by operation of the reactor from the performance specifications set forth in the technical specifications.
(2)
At least yearly, Yankee shall submit an operation report su.marizing data with respect to the following:
(a) Hours use of the reactor.
(b)
The electric output of the plant.
J (c)
Shutdowns of the reactor, with a brief explanation of the cause and duration of eabh shutdown.
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(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.
1 (f)
Routine releases, discharges and shipments of radioactive materials.
(g)
Principal maintenance performed with the reasons therefor.
I (h)
A description of significant tests performed and the results of any test analyses completed.
The tests reported shall include periodic determinations
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of the effects of plutonium build-up on reactivity coefficients and of reactor power distribution as measured by use of the in-core instrumentation.
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(i) Significant changes or new information regarding transient or accident analyses.
(j)
A description of any other significant or unusual occurrence or operating condition experienced.
(3)
Within 90 days following the end of each calendar year, Yankee shall submit a financial report for such year, including a balance sheet at the end of such year and a statement of income and surplus for such year; and a summary of the amount and type of financial protection
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in effect at the end of such year pursuant to section 170 of the Act.
Each such report sah11 be in writing, signed by a responsible officer of Yankee and shall be addressed to the Commission, r
l Attention:
Division of Licensing and Regulation.
25 copies of l
l each report shall be submitted.
Reports s,ubmitted pursuant to (1) above may be made initially by telephone, telegram or orally but shall be confirmed in writing promptly thereafter.
E.
Amendments to the License Application Yankee may submit amendmqnts to its license application at any time or from time to time, but no such amendment to the license l
application shall be effective to change or modify the technical l
l specifications unless authorized by the Commission pursuant to
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section 50.59 of the Regulations, Title 10 CFR, Chapter 1, Part 50.
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. 4.
Pursuant to section 50.60 of the Regulations, Title 10 CFR, Chapter 1, Part 50, the Commission has allocated to Yankee for use in the operation of the reactor 6,002.6 kilograms of uranium 235 contained in uranium at the isotopic ratios specified in Yankee's license application.
Estimated 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 accoraance with Column (2) in Appendix B will be conditioned upon Yankee's return
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to the Commission of material substantially in accordance with Column (3) of Appendix 3.
S.
This license is effective as of the date of issuance and shall expire November 4,1997.
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FOR Tile ATO5!IC ENERGY COSNISSION
[1
/s/ R. Lowenstein Director Division of Licensing and Regulation Attachments:
1.
Appendix A 2.
Appendix B Date of Issuance: October 11, 1962 u.
APPEND 1X A i-YANKEE ATOMIC ELECTRIC COMPANY I
1 Technical Specifications i
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j A.
SITE The reactor shall be located on the property owned by Yankee in_Rowe, i
Mass. The site includes the property owned by Yankee and New England i
Power Company as shown on the map on page 300:2 of the licehse applica-tion.
j No part of the site shall be sold or leased without the prior approval f
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
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except railroad facilities owned and used by the Hoosac Tunnel and Wilmington Railroad Company.
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B.
DESIGN SPECIFICATIONS 1
1.
The following sections of the licen'se application are considered to j
be design specifications of the reactor and are incorporated herein l
in their entirety:
4 101 Core Mechanical Design I
2 01 Main Coolant System l
202 Pressure Control and Relief System 203 Charging and Volume Control System 2 04 Chemical Shutdown System 210 Shutdown Cooling System j
212 Safety Injection System 1
230 Reactor Vessel
.2.
The pressures and temperatures used as a basis for design, materials of construction, general arrangements. of the systems and their com-ponents, 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 and Hydraulic Design 103 Core Nuclear Design 106 Reactor Coolant Chemistry 107 Core Instrumentation 205 Purification System 207 Corrosion Control System--Primary Plant 4
209 Radioactive Waste Disposal System 213 Reactor Control System 214 Nuclear Instrumentation System 215 Radiation Menitoring System 218 Fuel Handling System 224 Compressed Air Systems 231 Vapor Contairment 232 Radiation Shielding 235 Architectural-Features
... _ _ _ - -~ __ _, -,_,,.,.___.
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(1 Physical arrangements of structures and equipment will be as described in Sec, tion 200 of the license application. Mechanical equipment and systems will be interconnected as shown in the Fundamental Flow Diagram included in that section.
Electrical equipment and systems which provide station axuiliary 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 labora-tory, decontamination cubicle, fuel transfer pit house, and other potentially contaminated portions of the Turbine Generator, Service, e
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, temperatures, 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 refer-ence herein. Yankee shall not operate the facility under circumstances where there is a subrtantial 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 componehts 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 provision of these Technical Specifications.
206 Component Cooling System 208 Sampling System 211 Vent and Drain System, Primary Plant 216 Vapor Container Atmosphere Control Systems 219 Main and Auxiliary Steam System 220 Condensate and Feed Water Systems 221 Circulating Water System 222 Wa+er Supply System D.
OPERATING PROCEDURES AND RESTRICTIONS 1.
Oceratino procedures The reactor will at all times be operated in accordance with generally accepted standards of safe operating procedure, subject to the opera-ting restrictions set forth below. All operations will be conducted in accordance with written procedures and under the direct and personal
' supervision of technically qualified and designated personnel.
.The Objective, Conditions and Precautions set forth in the individual instru,ctions contained in the following sections of the license appli--
cation will be observed:
504 Normal Plant Operation Instructions 505 Emergency Instructions j
i 506 Plant Maintenance Instructions j
2.
Operatino Limits i
a.
Reactivity s
(1) During core loading the fuel assemblies, control rods and s'.iim rods will be loaded one by one in water. sufficientl torated to render the fully loaded core at least 5% d K/y i
K sub-critical at room temperature.
l (2) During the refueling operation a record will be made of the neutron count rate before and after any change in core geom-etry.
If a significant unexpected increase in the count rate occurs on any one channel or if an unexpected increase in the l
count rate by a factor of two on two of the three channels 4
occurs after addition of a new fuel assembly or removal of a control rod, the fuel loading operation will be suspended until the situation can be reviewed by plant technical super-visory personnel.
If necessary to establish the shutdown margin of the core, a single control rod will be withdrawn using the manipulator crane and regulated by a plot of con-trol rod positior' vs. inverse count rate multiplication.
Using the inverse count rate data obtained in this manner, the shutdown margin will be calculated.
If tbase calcula-tions indicate that there will be less than 5% d K/r, shut-down with all control rods incerted in the fully loaded core, the boron concentration will be increased to provide the j
required 5% 8 K/K shutdown margin.
l (3) At all times when the reactor is at operating temperature l
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% d 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% 8 K/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 red.uction of boric
' acid concentration in the, main coolar:t system through dilution will not exceed 1.5 x 10 " d K/K per second, i
a 4-j (6) Whenever the reactor is shut down, before any operation which might result in a change of reactivity, a control rod group shall be withdrawa to a height sufficient to provide a reactivity worth of 1% for emergency shutdown capability.
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4 If for any son this is not practical, the main coolant Laboratedtoprovide5%/hK/Kcoldshutdown system sha 1
margin witi all control lods inserted.
(7) The rea~'or will be scrammed automatically below 15 MW elec-tric i
high startup rate signal set at a maximum of 5.2 decades / minute, b.
power Level (1) The steady state power level of the reactor will not exceed rated power of 540 MW thermal, (2) The riactor will be scrammed automatically by a high neutron flux '.evel signal, set at not more than 108% of rated power as defined in (1) above.
j (3) During operation with one loop of the four main coolant loops isolated from the system, the steady state thermal power level
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of the reactor will not exceed 378 MW thermal.
(4) During operation with one main coolant loop isolated, the reactor will he scrammed automatically by a high neutron flux level signal, F t at not more than 108% of the power level defined in (3) above.
(5) Except fc-operation of the *.c+0r at power levels not ex-ceeding 15 MN electric, the reactor shall not be operated with less than three main coolant loops in service.
c.
Thermal (1) At rated power the calculated heat flux at the point clesest to burnout in the hottest channel shall not exceed 50% of the burnout heat flux as predicted by the "W-2" correlation, shown on page 102:19 of the license application. This ratio shall be checked every 1000 equivalent full power hours of operation utilizing data derived from the in-core instrumen-tation.
(2) Atratedpowerthecalculatedtemperatureofthecoogantat the exit of the hottest channel shall not exceed 609 F.
l (3) At rated power the calculated maximum clad surface tempera-ture in the hottest channel shall-not exceed 663 F.
e.
Main Cool _ ant System (1) The reactor will be scrammed automatically above 15 MW clec-tric by a low main coolant pressure signal set at a minimum of 1800 psig.
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t (2) The. reactor will be scrammed automatically above 15 MW electric by a low main coolant flow signal. Low flow
' scram will be-initiated by low flow in not more than two of four loops for operation at or below 485 Kn t. Low i
flow scram will be initiated by low flow in one of four loops above 485 MWt. A loop low flow condition is de-fined as 60% or less of normal flow in the loop.
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(3) The reactor will be scrammed automatically by a high pressurizer water level signal set at a maximum of 200 inches whenever the turbine generator is operating.
i (4) The reactor will nc' 5-brought to criticality at a main coolant system temperature lower than 250 F except for i
scheduled low power physics testing which v:111 be performed l
in accordance with written procedures.
1 (5) During normal plant startup boric acid dilution will not be commenced until the main coolant system temperature has reached equilibrium at 250 F.
(6) The plant will not be operated at loads above 15 MW electric unless the boron concentration in the main coolant system is l
less than 80 ppm. The plant will not be operated below 15 MW I
electric with more than 220 ppm of boron in the main coolant l
system except during normal startups or during low power physics testing which will be performed in accordance with written procedures.
(7) Whenever a main coolant loop is isolated fram the system, it will be borated at full shutdown concar'.;ations before its temperature is reduced below 485 F.
(8) An isolated main coolant loop will be returned to service only after the boron concentration and the water temperature have been closely matched to existing main coolant system i
conditions. An automatic valve interlock prevents any iso-lated loop from being, returned to service if the loop temper-ature is more than 30 F lower than the highest cold leg temperature in the other loops.
Other Plant Protection e.-
(1) The reactor will be scrammed automatically, above 15 MW elec-tric, when tSt turbine is tripped for any reason..The turbine will be protected by all usual protective trips including high l
thrust bearing temperature, low bearing oil pressure, low con-j denser vacuum and overspeed.
i (2) The reactor will' be scrammed automat $ cally, above 15 MW elec-tric when the generator is tripped for any reason. The gen-erator will be protected by all usual protective trips includ-ing overcurrent, differential and loss of field.
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(3). The safety injection system will 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 will automatically initiate operation of the motorized valves in this sytem and a pressure switch set at not less than 800 psig main coolant pressure will automatically start the high pressure safety injection pump, and a second pressure switch set at not less than 270 psig main coolant pressure will auto-matica11y start the low pressure safety injection pumps.
(4) The boiler feed pumps will be automatically tripped out of service, above 15 VX electric, by any reactor scram.
i (5) Valves in all outgoing lines from the vapor container will close automatically if at any time vapor container pressure increases above'5 psig.
(6) The integrity of the vapor container will 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 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 conserva-tive values of the particular variables being measured. Table I also shows the number of channels associated with each func-
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tion 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 will continue regular operation.
The scram circuits, however, will then operate so that activation a
j of any of the remaining channels for that function will cause i
- qam operation.
f.
Plant Protection when the Reactor Vessel Head is Removed and the Vessel Contains Fuel.
(1) All operations will be conducted in accordance with written procedures.
(2) The water in the reactor vessel and in the shield tank cavity will be sufficiently borated to render the core at least 5%
/hK/Ksub-criticalatroomtemperature.
(3)- L'ormal plant source range instrumentation will be in service at all times with the count rate recorded and a startup rate alarm set at 1 decade / minute.
(4) -An AEC licensed operator will be on duty in the control room at all times.
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(5) The chemical shutdown system will be lined up snd available at all times to provide emergency shutdown under the control j
of the AEC licensed cperator.
(6) Equipment which would make possible inadvertent reactivity changes will be made inoperable and tagged out of servi,e.
(7) -Manipulation of reactor vessel components or internals will be carried out under the direct and personal supervision of j
technically qualified and designated personnel.
i g.
Waste Effluents (1) Solids -- No radioactive solid wastes will be disposed of at j
the site.
(2) Liquids -- No radioactive liquid wastes having concentrations in excess of those specified in Appendix B., Table II, 10CFR20, j
will 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, the concentrations of radioactive gaseous wastes l
discharged shall not be in excess of 1,000 times the limits specified in Appendix.B, Table II, 10CFR20. Any discharge to the atmosphere from the gas stripper or the combustible waste incinerator 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 in order to provide an alarm and a record in the event of the release of radioac-p tive gas frem the waste disposal blanket gas system through the loop seal.
h.
Radioloolcal Health and Safety Personnel radiation exposures will be maintained below the limits 4
established in Title 10, CFR 20, or in any future amendments to this regulation.
- i. Routine and Continuino Tests Routine and periodic tests will be made at the times and in the I
manner set forth.in Section 509 of the license application.
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Att.
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TABII I l'EACTN MIOTNf.i!O" V T POI 7TS No. of Channela Functien Required to Trip Bypasses Set Point Liaits Rearks:
- ligh Startup Rate -
1 out of 2 Auto bypass 5 2 dec/atn - max acacter Scrira Above 15 ree high heutron 2 out of 6 Eme hutron flux corresponds to liinimx1 of h operable channels Flux levei -
1081 rated power - mar required fo: reactor operation.
React <r Scrar Wutron nux 1 out of 6 Auto bypass Irrel Decrease-Below 15 PNe Neutron flux decrease corresponding neacter Scran to 15% of SLO f % - max Low kain Cociant 1 out of 2 Auto bypass 1800 psig - min Pressure -
Brica 15 Wee Heretcr Scram No e han Pain Coelant Auto bypass 60% of normal main coolant b'IO" 15 YA' below la85 P'Wtj flow in any loop - min d
tor Scras 1 out of L above h85 f#t i.igh Pressurizer 1 out of 1 Manual 200 inches - maz In servlee ehenever turbine Cater tryc1 -
generater is operating.
Retetor Scram kanutt -
hot Applicable None Availabla any tian 3eacter Scram Turbine Trip -
Not Applicable Auto bypass Usual Turbine Trip set points Turbine trip seraas react <r armi du ctor Germ klos 15 F4e trips generatcr sbove 15 ree.
Genrrator Trip -
Not Applicable Auto bypass Usual Generator Trip set points Generator trip scrass reacter a.nd darcter Scram Belom 15 De trips turbine above 15 r6e.
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- Lanual Turbine Not Applicable Auto bypass Available any time above 15 ne gGen<r ator Trip -
Below 15 Fee
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Acacter Scrac.
mKhSafety Ir.jecticn 1 out of 1 Nanual 800 psig main coolant pressure-ctin During normal creration system is Operation (motorized valves and high pressure set for autcaiatic initittion.
pump operate)
Safety injection may be initiated
_n c6 270 psig main coolant pressure-min sanually at my time.
(low pressure pumpe start) g,,,_.2 hhreasurizer Not Applicable None 2h85 peig, No. 1 Valve - max c-m arcty valve 2560 psig, No. 2 valve - max cp peration d-1 out of 2 None 5 reis varer container rressure-.=x Closes trip valves in cutgoins
- V2por Container lines in vapor container.
{dutgoing Line Trip.
alve Operation rain Coolant valve Not Applicable None 30 F temperature differential - max Freventa any isolated log frm being placed into operation if the inter 1cck 0
Icop temprature is mere than 30 F louer than highest cold leg tespra-n ture in tte reo.atning lecps.
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i APPENDIX B v.
Estimated Schedule of Transfers of Special Nuclear Material frem the Commission to Yankee and to the Commission from Yankee:
(1)
(2)
(3)
(h)
(5)
Not Icarly Cumu).ative Distributier Distribution Date of Tranafers Including Inciuding Transfer from AEC Returno by Yankoe Cumuintive cumulative (Tiocal toYankee(a) toAE0(b)
Losses Losses Year)
Kgs. U-235 Ege.'U-23$
Egs.U-23$
Egs. U-235 208.8 208.8 1959 208.8 590.2 799 0 1960 590.2 719.1 1,518.1 1961 719 1 1962 803.1 6232(o) 179,9 1,698.0 1963 5b5.9 (5b5 9) 1,152.1 196b 81h.3 622.8 191.5 1,3h3.6 815.0 2,158.6 1965 815.0 1966 622.8 (622.8)-
1,535.8 1967 815.0 622.8 192.2 1,728.0 815.0 2,563 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' 015.0 622.0 (622.8) 2,30h.6
'972 1973 015.0 622.8 192.2 2,b96.8 815.0 3,311.8 197h 815 0 1975 622.8
('622.8) 2,698.0 19 %
815.0 622.8 192.2 2,861.2 815.0 3,696.2 1'j77 815.0 622.8 (622.8) 3,073.h 978 1
1979 815.0 622.8 192.2 3,265 6 815.0 h,080.6 1900 815.0 622.8 (622.8) 3,b57.0 1981 1982 815.0 622.8 192.2 3,650.0 815.0 h,h65.0 1983 815.0 19eh 622.8 (622.8) 3,8h2.2 1985 815.0 622.8 192.2 h,03h.h (c tinued) t on
Appondi
".D' (Continued) (1)
(2)
(3)
(h)
(5) 1986 '
815.t/
815.0 h, Bhp,4 1987 622.8 (622.8) h 226.6 1988 B.' 5.0 622.8 192.2 h,,h18.8 1989 815.0 815.0-5,233.8 1990 622.8 (622.8) h,611.0 1991 815.0 622.8 192.2 h Bo3.2 1992 815.0 815.0 5,618.2 1993 622.8 (622.8).
h,,995.h 199h 815.0 622.8 192.2 5,167.6 1995 815.0 e
815.0 6
622.8 (622,.8) 5,002.6 1996 379.8 1997 815.0 622.8 192.2 5,572.0 1998 622.8 (622.8) h,9h9.2 1999 61.2 *(n)
( 61.2)
__ h,,888.0 **
21,065.5 16,177 1 h,G88.0 **
3.h5 U-235 c
2.655 U-235 3.025% D-23$(Hot Fuol))except (c) and (a) b (HotFuel o
- Inve,ntory to be returned
"* Fabrication and burnup losses
%