ML20246L802: Difference between revisions

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| document type = OPERATING LICENSES & AMENDMENTS, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES & AMENDMENTS, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 5
| page count = 5
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| stage = Other
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Latest revision as of 04:02, 5 October 2021

Amend 5 to License R-123,allowing Postponement of Surveillance Requirements If Reactor in Unloaded State
ML20246L802
Person / Time
Site: University of Virginia
Issue date: 03/15/1989
From: Chris Miller
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246L798 List:
References
R-123-A-005, R-123-A-5, NUDOCS 8903240280
Download: ML20246L802 (5)


Text

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>3 *l00 l 9

kg UNITED STATES

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NUCLEAR REGULATORY COMMISSION

7. :j WASHINGTON, D. C. 20555
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UNIVERSITY OF VIRGINIA DOCKET NO. 50-396 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. R-123

1. The Nuclear Regulatory Comission (the Comission) has found that: l A. The application for amendment to Facility Operating License I No. R-123 filed by the University of Virginia (the licensee),

dated November 22, 1988 as supplemented on January 12, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations as set forth in 10 CFR Chapter I, j 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: (1)thattheactivitiesauthorized 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 Comission'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. Publicatfor. 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 i Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of License No. R-123 is hereby i 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 shal? cperate the facility in accordance with the Technical Specifft '.iGis.

3. This license amendment is effective as of its date of issuance.

FOR THE ilVCLEAR REGULATORY COMMISSION Y.AcYY Charles L. Miller, Director Standardization and Non-Power i

Reactor Project Directorate Division of Reactor Projects - III, IV,

. Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

4 Appendix A Technical Specifications Changes Date of Issuance: March 15, 1989 i

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l ENCLOSURE TO LICENSE Af1ENDMENT NO. 5 FACILITY OPERATING LICENSE NO. R-123 DOCKET NO. 50-396 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 16 16 16a e

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4.0 SURVEILLANCE REQUIREMENTS Aeolicability The surveillance requirements specified in Sections 4.1, 4.2, 4.3, 4.4, and 4.5 are applicable to time periods during which the i CAVALIER core is loaded. The specification below is applicable  ;

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, whenever the CAVALIER core is unloaded.

Specification All scheduled surveillance requirements falling due when the CAVALIER core is in an unloaded state may be postponed until such time that the core is to be reassembled. Postponed surveillance not requiring fuel elements on the gridplate shall be completed before fuel is moved to load the core. Other due surveillance requiring fuel elements on the gridplate shall be completed as per  ;

the individual specifications.

The CAVALIER core shall not be left in a partially loaded condition for more than one calendar week.

Ob-lectives Postponement of suweillance requirements whenever the core is

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unloaded permits suspension of CAVALIER operations for an indefinite period of time, until the use of the reactor is again required, or until the reactor is permanently taken out of service.

In addition, the CAVALIER core should not be left in a partially .

loaded condition for an indefinite time period.

Basis j since CAVALIER fuel elements can be indefinitely and securely stored in the Reactor Facility's Fuel Storage Room, maintaining the CAVALIER in an unloaded state is a viable option. The other option, that of maintaining an operable reactor, may not always be desirable or even possible. For example, a lack of fuel may exist, the type of fuel authorized for use may be changed by an NRC order, or the reactor could be in a decommissioning or pre-decommissioning stage.

An interval of one calendar week for loading or unloading the core is reasonable and provides flexibility to accommodate unforeseen circumstances.

Amendment No. 5

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4.1 Shim Rods Applicability This specification applies to the surveillance requirements for the shim .

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rods.

Objective To assure that the shim rods are capable of performing their function )

and that no significant physical degradation in the rods has occurred.

Specification ,

(1) Shim rod drop times shall be measured semi-annually. Shim rod drop times shall also be seasured if the control assembly is moved to a new position in the core or if maintenance is performed on the mechanism.

(2) The shim rod reactivity worths shall be measured whenever the rods  ;

are installed in a new core configuration.

Bases The reactivity worth of the shim rods is measured to assure that the required shutdown margin is available and to provide means for determining the reactivity wo.rths of experiments inserted in the core.

t The red drop times are seasured to assure that they meet the requirements of section 3.7 of these Technical Specifications.

4.2 Reactor Safety System Applicability j

This specification applies to the surveillance requirements for the safety system sessuring channels and associated circuits of the reactor safety system.

Amendment No. 5 I