ML19331C055
| ML19331C055 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 07/31/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19331C053 | List: |
| References | |
| R-095-A-008, R-95-A-8, NUDOCS 8008140103 | |
| Download: ML19331C055 (5) | |
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NUCLEAR REGULATORY COMMISSION gl4, {f,d f l./, j WASHINGTON, O. C. 20555
.,l RHODE ISLAND AND PROVIDENCE PLANTATIONS ATOMIC ENERGY COMNISSION 00CKET NO. 50-193 AMENDMENT TO FACILITY LICENSE Amendment No. 8 License No. R-95 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Rhode Island and Providence Plantations Atomic Energy Commission (the licensee) dated September 5,1979, 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; S.
The facility will operate in conformity with the application, the provisions of the Act, 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 end.ingering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Ccmmission's regulations; D.
The issuance of this amendment 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 requiremencs 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 Specifications as indicated in the attachment to this license amendment, and paragraph 3.b. of Facility License No. R-95 is hereby amended to read as follows:
b.
Technical Soecifications The Technical Specifications contained in Appendix A, issued July 21, 1954, as revised through Amendment No. 3, 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 REGULATORY CCMMISSION James,R. Miller, Chief Standardization & Special Projects Branch Division of Licensing
Attachment:
Changes to the Technical Speci ficatf or s Date of Issuanen: July 31,1980
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l ATTACHMENT TO LICENSE AMENDMENT NO. 8 FACILITY OPERATING LICENSE N0'. R-95 00CKET NO. 50-193 Replace Pages 7 and 29 of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment Number and contain a vertical line indicating the area of change.
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REACTOR COPE AND CONTROL ELEMENTS The reactor core and control elements shall.have the following charac-teristics and nominal dimensions:
Princioal Core Materials Fuel matrix Alloy, UA1, U 0 3
38 U-235 enrichment Approximately 93P, Fuel clad 1100 and/or 5061 aluminum Fuel element side plates 6061 aluminum End fittings 355-T5 or 6061 aluminum Modera tor Water Reflector AGOT grade graphite and/or water Control elements Mixture of 8 C and aluminum, clad 3
with aluminum Servo Element Mixture of 3 C and aluminum, clad 3
with aluminum.
2.
Fuel elements Plate width overall 2.8 in.
Active plate width 2.2 in.
Plate length overall 25 in.
Active plate length 24 in.
l Plate thickness 0.06 in.
Cl.d thickness 0.02d in.
Fuel matrix thickness 0.012 in.
Water gao between plates 0.1 in.
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l Amendment No. 3 r
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(e) Servo Regulating Element Drive Performance Reouirements If in use during operation, the servo regulating element drive shall meet the following specifications:
1.
The drive withdrawal rate shall not be more than 78 inches per minute.
2.
It shall be demonstrated at least once per month that the above specification is met.
(f)
Fission Density Limit The fission density limit for alloy, uranium aluminide, and uranium oxide fuel shall meet the following speciff-cations:
21 1.
The fission density limit shall be 0.5 x 10 fissions /cc.
2.
The fission density of all fuel elements which have burnup shall be calculated at least quarterly.
f.
Reactor Safety Systems (1) The reactor safety system shall be operable during all reactor operation. The safety system shall be checked out before each start-up and functionally tested for calibration at least monthly.
(2)
It shall be permissible to continue operations with one or more of the safety system functions that produce only an alarm temporarily disabled providing that additional procedural controls are instituted to replace the lost safety system alarm function (s).
(3) The control element withdrawal interlocks and the servo system control interlocks shall be functionally tested at least once per month.
(4) During reactor startup or during mechanical changes that could affect core reactivity, the startuo range neutron monitoring channel shall be operable and shall provide a neutron count rate of at least 3 counts per second with a signal to noise ratio at least 3 to 1.
(5) The linear level safety channels shall not read less than 15% of full scale when the reactor is operating at power levels above I watt.
(6)
Following a reduction in power level, the operator shall adjust the servo power schedule to the new power level before switching to automatic operation.
(7) An alarm condition from any one of the items listed Section F.2.b.
after working hours shall transmit coded information :o a continuously manned central station in ?rovidence, Rhooe Island. The central station shall be provided with written instructions on the stecs to te taken following an alarm.
Amendment No. 3
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