ML20217N214

Amend 17 to License R-76,updating Reporting Requirements in TSs to Be Consistent W/Current NRC Guidance for Research Reactors

ML20217N214
Person / Time
Site:	Washington State University
Issue date:	04/03/1998
From:	Mendonca M NRC (Affiliation Not Assigned)
To:
Shared Package
ML20217N203	List: ML20217N197 ML20217N214 ML20217N220
References
R-76-A-017, R-76-A-17, NUDOCS 9804090046
Download: ML20217N214 (5)

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UNITED STATES NUCLEAR REGULATORY COMMISSION s

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WASHINGTON. D.C. 20565-0001

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l WASHINGTON STATE UNIVERSITY DOCKET NO. 50-27 AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No.17 l

License No R-76 l

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to Facility Operating License No. R-76 filed by l

the Washington State University (the licensee). dated February 20,1998, l

complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set i

forth in 10 CFR Chapter I; l

B.

The facility will operate in conformity with the application, the provisions of the l

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 l

public and (ii) that such activities will be conducted in compliance with the Commission'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; i

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the

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l Commission's regulations 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.

9004090046 980403 PDR ADOCK 05000027 P

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4 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment. Station 2.C(2) of Facility

. Operating License No. R-76 is hereby amendeo to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.17, 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 e %.%~~-~h%, /m t r

Marvin M. Mendonca, Acting Director Non-Power Reactors and Decommissioning

~ Project Directorate-Division of Reactor Program Management Office of Nuclear Reactor Regulation '

Enclosure:

Appendix A Technical Specifications Changes Date of issuance:

April 3, 1998 l

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ENCLOSURE TO LICENSE AMENDMENT NO.17 FACILITY OPERATING LICENSE NO. R-76 DOCKET NO. 50-27 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain verticallines

- indicating the areas of change.

Remove Pages insert Pages 35 & 36 35 & 36 l

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6.10 Reoortinc Reauin ments In addition to the requirements of applicable regulations, and in no way substituting for those requirements, reports shall be made to the Nuclear R.egulatory Commission as follows:

(1)

A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone to the NRC Operations Center, of l

(a)

Any accidental release of radioactivity above permissible limits in unrestricted areas whether or not the release resulted in propeny damage, personal injury, or exposure; (b)

Any violation of the safetylimit; (c)

Any reportable occurrence as defined in Section 1.1, " Reportable Occurrence," of these specifications.

(2)

A repon within 10 days in writing to the USNRC Document Control Desk, Washington, D.C. 20555, of (a)

Any accidental release or radioactivity above permissible limits in unrestricted areas whether or not the release resulted in propeny damage, personal injury, or exposure. The written report (and, to the extent possible, the preliminary telephone or telegraph report) shall describe, analyze, and evaluate safety implications, and outline the corrective measures taken or planned to prevent recurrence of the event; (b)

Any violation of a safety limit; (c)

Any reportable occurrence as defined in Section 1.1, " Reportable Occurrence," of these specifications.

(3)

A report within 30 days in writing to the USNRC Document Control Desk, Washington, D.C. 20555, of (a)

Any significant variation of measured values from a corresponding predicted or previously measured value of safety-connected operating characteristics occurring during operation of the reactor, (b)

Any significant change in the transient or accident analysis as described in the Safety Analysis Repon; (c)

Any significant changes in facility organization; (d)

Any observed inadequacies in the implementation of administrative or procedural controls.

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(4)

A report within 60 days after completion of startup testing of the reactor (in writing to the USNRC Document Control Desk, Washington, D.C. 20555) upon rec a new facility license or an amendment to the license authorizing an increase reactor power level describing the measured values of the operating conditions including:

(a)

An evaluatire of facility performance to date in comparison with design predictions and specifications; (b)

A reassessment of the safety analysis submitted with the license application in light of measured operating characteristics when such measurements indicate that there may be substantial variance from prior analysis.

(5)

An annual repon within 60 days following the 30th of June of each year in writing to the USNRC Document Control Desk, Washington, D.C. 20555, providing the following information:

(a)

A brief narrative summary of(i) operating experience (including experiments performed), (ii) changes in facility design, performance characteristics, and operating procedures related to reactor safety and

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occurring during the reporting period, and (iii) results of surveillance tests and inspections:

(b)

Tabulation of the energy output (in megawatt-days) of the reactor, hours l

reactor was critical, the cumulative total energy ouput since initial criticality, and number of pulses greater than 1.00$;

(c)

The number of emergency shutdowns and inadvertent scrams, including reasons for them; (d)

Discussion of the major maintenance operations performed during the period, including the effect,if any, on the safety of the operation of the reactor and the reasons for any corrective maintenance required:

(e)

A brief description, including a summary of the safety evaluations of changes in the facility or in procedures and of tests and experiments carried out pursuant to 10 CFR 50.59:

(f)

A summary of the nature and amount of radioactive effluents released or dischvged to the environs beyond the effective control of the licensee as meamted at or before the point of such release or discharge:

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