ML20051E451
| ML20051E451 | |
| Person / Time | |
|---|---|
| Site: | 05000054 |
| Issue date: | 05/06/1982 |
| From: | Bernard H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20051E361 | List: |
| References | |
| R-081-A-016, R-81-A-16, NUDOCS 8205170026 | |
| Download: ML20051E451 (4) | |
Text
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sCS ** G Vq'g UNITED STATES g
NUCLEAR REGULATORY COMMISSION J
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UNION CARBIDE SUBSIDIARY B, INC.
DOCKET N0.
50-54 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 License No. R-81 r
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Union Carbide Subsidiary B, Inc.
(the licensee) dated June 2,1981 and supplemented January 9,1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I.
B.
The facility will operate in conformity with the provisions of the Atomic Energy Act of 1954, as amended, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendent will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and F.
Publication of notice of this amendment is not required since it does not involve a significant hazards. consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
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2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 3.5.2.c(5) and paragraph 3.5.2.d of Facility Operating License No. R-81,is he'reby amended to read as follows:
'rESIGUATED ORIGIN b
Certifica E7 205170 @ C"
(2) Technical Specifications The Technical Specifications, as revised through Amendment No.16, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGUL ORY COMMISSION
/
d Harold Bernard, Acting Branch Chief Standardization & Special Projects Branch Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: MAY 0 61982 4
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19.
b.
Objectives - The objective is to prevent damage to the reactor, prevent excessive release of fission products in the event of an experiment failure, and also to en-sure that safety limits are not exceeded.
c.
Specifications - Fuel-bearing experimbnts in the' reactor shall meet the following conditions:
(1) All fueled experiments.are to conform to the specifications listed above in Section 3.5.1.
(2) The inventory of solid fuel bearing material being irradiated in the reactor core at any time shall be limited to 200 g of source and/
or 750 g of special nuclear materi6l.
(3) The inventory of solid fue.1-bearing materials in a single irradiation capsule shall be limited to 200 g of source and/or 50 g of special nuclear materi al.
(4) The fission power of an irradiation capsule containing special nuclear material shall be limited to 13 KW.
(5) The iodine inventory of a singly encapsulated capsule shall be limited to a maximum of 1000 curies 1-131 dose eqbivalent.
d.
Bases - These specifications ' place limits on 'the fission
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product inventorycin a fueled vipsula such that capsule failure and.the hypothetical release of all contained fission products to the rea'ctor coolant will not result in excessive exposure to personnel'on and off site.
The deta[ led analyses that' form the bases of this speci-fication are given in References in Section 7.
The total l
amount of special nuclear material permitted in the core
.at any' time has been increased to 750 g.
This increase does not i
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55.
7.0 REFERENCES
. Supplement No. 2 to Final Hazard Summary Report (April 1977).
1.
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2.
Final Hazards Summary Report (May 1960).
3.
Reactor Power Excursion Tests in the SPERT IV Facility, ID0-l
- 17000 (Aug. 1964).,
e 4.
Supplementary Information to Final Hazards Summary Report (28 April 1961).
l, L'
5.- ' Critical Experiments with SPERT-D Fuel Elements, ORNL-TM-1207
. by E. B. Johnson and P. K. Reedy, Jr.
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(July 14,1965),
6.
Supplement No. 3 to Final Hazard Summary Report (December 1977).
7.
Supplement No. 4 to Final Hazard Summary Report (April 1978).
8.
Safety Evaluation Report for Union Carbide Request for Single Encapsulation for In-Core Iodine Production and Increase to.
1000 Ci per capsule.
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