ML20153A911
| ML20153A911 | |
| Person / Time | |
|---|---|
| Site: | Berkeley Research Reactor |
| Issue date: | 07/05/1988 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20153A896 | List: |
| References | |
| R-101-A-005, R-101-A-5, NUDOCS 8807120654 | |
| Download: ML20153A911 (5) | |
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UNITED STATES t f g NUCLEAR REGULATORY COMMISSION 5 t E WASHINGTON, D. C. 20665 a !
UNIVERSITY OF CALIFORNIA AT BERKELEY DOCKET NO. 50-224 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. R-101
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to Facility Operating License No.
R-101 filed by the University of California at Berkeley (the .
licensee), dated June 26, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; 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 set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the comon 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 Comission'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).
8807120654 880705 PDR ADOCK 0500C'24 P PDL
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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, and paragraph 2.C.2. of License No. R-101 is hereby amended to read as follows:
- 2. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 5, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
i.J-e $j h( ~ %T 3 Lester S. Rubenstein, Acting Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Prcjects Office of Nuclear Reactor Regulation 1
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance: July 5, 1988 l
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ENCLOSURE TO LICENSE AMENDMENT NO. 5 FACILITY OPERATING LICENSE NO. R-101 DOCKET NO. 50-?24 Replace the following page 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.
Remove Page Insert Pages 18 18 18a l
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- ,- s 4.0 SURVEILLANCE REQU
- REMENTS 4.1 GENERAL 4.1.1 Proper Operation of Systems Applicability This specification applies to the surveillance requirement of any system related to reactor safety.
Objective ,
The objective is to verify the proper operation of any system re13ted to reactor safety.
Specifications Any additions, modifications, or maintenance to the ventilation system, the core and its associated support structure, the pool or its penetrations, the pool coolant system, the rod drive mechanism, or the reactor safety system shall be made and tested in accordance with the specifications to which the systems were originally designed and fabricated or to specifications approved by the Reactor Hazards Comittee. A system shall not be considered operable until after it is successfully tested.
Bases This specification related to changes in reactor systems which l could directly affect the safety of the reactor. As long as changes or replacements to these systens continue to meet the l
original design specifications, then it can be assumed that they meet the presently accepted operating criteria.
4.1.2 Surveillance Postponements Applicability This specification applies to surveillance requirements that '
involve raising the control rods.
Objective l The objective is to postpone surveillance requirements that involve raising the control rods if the reactor has not been in operation.
Specifications Surveillance requircrrents that involve raising the reactor control rods may be postponed if the reactor has not been in operation for a period of time that causes the surveillance to be missed. Postponed surveillance requirements shall be verified upon reactor startup. This postponement does not apply to Specification 4.2.1 c.
l Amendment No. 5 l
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r g-Bases This specification allows operational flexibility and limits unnecessary operation of the reactor.
4.2 LIMITING CONDITIONS FOR OPERATION 4.2.1 Reactivity Requirements Applicability These specifications apply to the surveillance requirements for reactivity control of experiments and systems. )
Objective The objective is to measure and verify the worth, performance, and operability of those systems affecting the reactivity of the reactor.
Specifice.tions
- a. The reactivity worth of each control rod and the shutdown margin shall be determined bi-annually but at intervals not to exceed 28 months.
- b. The reactivity worth of an experiment shall be estimated or measured, as appropriate, before reactor operation with said experiment.
- c. The control rods shall be visually inspected for deteriora-tion bi-annually but at intervals not to exceed 28 months, i
-18a- Amendment No. 5
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