ML20203J781

Revised Tech Specs 6.10 Re Reporting Requirements

ML20203J781
Person / Time
Site:	Washington State University
Issue date:	02/20/1998
From:	WASHINGTON STATE UNIV., PULLMAN, WA
To:
Shared Package
ML20203G972	List: ML20203G967 ML20203J781
References
NUDOCS 9803040290
Download: ML20203J781 (2)

Text

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h e 6.10 Reporting Requirenants in addition to the requirements of applicable regulations, and in no way substituting for

- those requirements, reports shall be made to the Nuclear Regulatory Commission as follows:

(1). _ A ieport witHn 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::dioactivity 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 Ox:rrence," ot' these specifications.

(2) A repon v>ithin 10 days in writing to the USNRC Document Control Desk, l Was11ngton, D.C. 20555, of l (a) Any accidental release or radioactivity above pennissible limits in unrestricted areas whether or not the release resulted in propeny damage, personal injury, or exposure. The written " port (and, to the extent ~

possible, the preliminary telephone or telegraph report) shall descriN, analyze, and evaluate safety implications, and outline the correctJve measures taken or planned to prevent recunence of the event;

'(b) 'Any violation cf a safetylimit;

/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

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(a). Any significant variation of measured values fmm a corresponding predicted or previously incasured value of safety-connectec operating characteristics occurring during operation of the reactor; (b) Any significent change in the transient or acciaent analysis as described in the Safety Analysis Report; (c) Any signifk.c.. nanges in facility organir aion;

-(d)_ Any observed inade procedural controls.quacies in the implementation of administrative or

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

(a) An evaluation of facility perfonnance to date in comparison with design predictions and specincations; (b) A reassessment of the afety analysis submitted with the license application in light c,f measured operating characteristics when such measurements indicate that there may be substantial variance from prior analysis.

(5) An annual report 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 sununary of (!) operating experience (including experiments perfonned), (ii) changes in tacihty design, performance characteristics, and operating procedures related to reactor safety and occurring duiing the reporting period, and (iii) results of surveillance tests and inspections; a

(b) Tabulation of the energy output (in megawatt-days) of the reactor, hours reactor was critical, the cumulative total energy output since initial criticality, and number of pulses greater than 1.00$;

(c) Pe number of emergency shutdowns and inadvertent scrams, including reasons for them; (d) Discussion of the major nuiraenance operations performed tiaring 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; (O A summary of the nature and amount of radioactive ef0uents released or discharged to the environs beyond the effective control of the licensee as measured at or before the point of such relcaw or discharge:

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