ML20199E822
| ML20199E822 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 11/12/1997 |
| From: | Weiss S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199E820 | List: |
| References | |
| R-095-A-025, R-95-A-25, NUDOCS 9711240008 | |
| Download: ML20199E822 (4) | |
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F y* oaeog\* UNITED STATES
- ' NUCLEAR REGULATORY COMMISSION !
WASHINGTON. O.C. seteHOM
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RHODE ISLAND ATOMIC ENERGY COMMISSION DOCKET NO. 50193 AMENDMENT TO FACILITY LICENSE Amendment No. 25 License No R 95
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for an amendment to Facility License No. R 95 filed by the Rhode Island Atomic Energy Commission (the licensee) on October 2,1997, complies with the standards and requirements of the Atomic Energy Act of 1964, as amended (the Act), and the regulations of the Commission as set forth in Chapter I of Title 10 of the Code of Federal Reaulations (10 CFR);
B. 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 endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the regulations of the Commission:
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 the regulations of the Commission as set forth in 10 CFR Part 51, and all applicable requirements have been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105 and publication of notice for this amendment is not required by 10 CFR 2.106.
9711240008 971112 PDR ADOCK 05000193 P PDR ,
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, end paragraph 3.b of Facility Ucense No. R 95 is hereby amended to read as follows:
3.b Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 25, 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 issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
Seymour H. Weiss, Director Non Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes i Date of issuance: Novmber 12, 1997 4
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ENCLOSURE TO LICENSE AMENDMENT NO. 25 FACILITY LICENSE NO. R 95 !
DOCKET NO. 50193 i
Replacc the following page of the Appendix A Technical Specifications with the enclosed i page. The revised page is identified by amendment number and contains vertical lines indicating the area of change. '
Remove Peae insert Face 29 29 ,
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l TECHNICAL SPECIFICATIONS -I Rhode Island Nuclear- Science Center ,
Docket 50193. License R 95 Revision I reactor operation, fuel movement and handling of ;
radioactive materials in the reactor building.
Ob,lective-To assure. that radiation monitoring equipment is available for evaluation of radiation conditions and that the release of airborne radioactive material is maintained !
-below the lim.ts established in 10CFR20. .
Specification:
- 1. When the reactor is operating, gaseous and !
particulate sampling of the stack effluent shall be monitored by a stack monitor with a ,
readout in the control room. .
-The particulate activity monitor and the gaseous activity monitor for the facility :
. exhaust stack shall be operating. If either :
unit is out of service for more than one shift i (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />), either the -reactor shall be shut down or the unit shall be replaced by one of comparable monitoring - capability. t
- 2. When the reactor is operating, at least one constant air monitoring unit -(Table 3.2.11) located in the confinement building shall be operating. Temporary shutdown of this unit ,
shall be limited as in-3.7.1 above.
- 3. The reactor shall not be continuously
- operated without a - minimum of one area ,
radiation - monitor (Table 3.2.8) on -the experimental ' level of the reactor building and -
one area -monitor (Table - 3.2.6) over the reactor ' pool (reactor bridge) operating and capable of -warning personnel of high radiation levels. .
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