ML20042A836
| ML20042A836 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos File:GEH Hitachi icon.png |
| Issue date: | 03/22/1982 |
| From: | Darmitzel R GENERAL ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8203240183 | |
| Download: ML20042A836 (4) | |
Text
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GENER AL h ELECTRIC
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ENGINEERING I
GENERAL ELECTRIC COMPANY, P.O. DOX 460, PLEAsANTON, CALIFORNIA 94566 DIVISION March 22, 1982 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.
C.,
20555 Ref:
- 1) License TR-1, Docket 50-70
- 2) Request for Technical Specification Changes, R. W. Darmitzel to D. G. Eisenhut, 2/4/82
Dear Mr. Eisenhut:
On February 4,1982, the General Electric Co. requested several changes in the Technical Specifications for the General Electric Test Reactor (GETR). These proposed changes eliminate certain tests which are not necessary with the reactor in its present shutdown condition and allow certain repirs and modifi-cations to be performed.
The proposed changes are based on the premise that the plate type fuel which was removed from the core in October,1977, no longer has a potential of re-leasing radioactive material if loss of storage canal water were to occur.
In support of this position, General Electric submits the attached information to demonstrate the current status of the fuel.
Sincerely,
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t? cpq 9?D,9 R. W. Darmitzel, Manager
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i 8203240183 820322 PDR ADOCK 05000070 P
8 AFFIRMATION The General Electric Company hereby submits the attached information in sup-port of its application dated February 4,1982. To the best of my knowledge and belief, the information contained herein is accurate.
U Cl?n R. W. Darmitzel, Manager Irradiation Processing Operation Submitted and sworn before me this [(44dde/eN day of March,1982.
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l SUPPLEMENTAL INFORMATION 'lT) THE
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PROPOSED CHAhGES IN THE TECHNICAL s
s SPECIFICATIONS FOR THE GETR, 2/4/1982 s
LIn order to provide up-to-date information as to the current thermal peri-meters of the GETR irradiated fuel, the fuel was analyzed using computer program RIBD, Version 1.
The RIBD code is a Fortran IV program which computes the fission product inventory of irradiated fuel by implementing a variation s
of Bateman's solution. The activities and concentrations of up to 450 isotopes are computed,at shutdown and at selected times following shutdown.
Irradiation history xis specified by an unlimited number of step changes \\ in power level.
Inputs parameters are operating power (MW), operating time at power, thermal flux of the first power step, the U-235 thermal absorption cross-section (494 barns),
(6.6446x10ghedecaytimesinceshutdown,andtheU-239'productionrate g/ MWD).
Due to time-constraints, not all elements were run, and the attached table shows representative elements. However, the element with the highest decay heat. (F611) is included.
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SUMMARY
OF RIBD RESULTS FOR SELECTED GETR FUEL ELEMENTS Element No.
Activity (Ci)
Thermal Power (Watts)
C5 909 2.74 C6 896 2.70 C7 1035 3.18 C8 1034 3.17 C9 600 1.80 C10 622 1.86 C11 654 1.96 C12 637 1.91 Cl3 744 2.61 C14 460 1.37 C15 424 1.26 C16 1192 3.68 C18 735 2.23 C19 731 2.22 C139 1040 3.04 C148 892 2.64 C149 898 2.66 F10 1579 4.77 Fil 1171 3.47 F12 2655 8.20 F13 1150 3.41 F14 1578 4.75 F15 1623 4.90 F16 2659 8.21 F17 1113 1.32 F18 1118 3.34 F19 1182 3.56 F20 1054 3.14 F21 1890 5.76 F22 1424 4.30 F23 1385 4.18 F24 1103 3.30 F25 892 2.66 F26 850 2.53 F28 1189 3.56 F29 1225 3.69 F30 1311 3.94 F31 1190 3.57 F32 741 2.21 F509 2087 5.90 F516 1832 5.19 F517 1694 4.81 F518 2753 8.51 F606 2905 8.95 F609 2618 7.98
- F611 3128 9.68
- Highest element
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