ML19312B800
| ML19312B800 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/02/1977 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19312B799 | List: |
| References | |
| NUDOCS 7911190582 | |
| Download: ML19312B800 (1) | |
Text
, 6.6*.2 Non-Routine Reports 6.6.2.1 Reportable Occurrences a.
Prompt Notification with Written Followup The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery by telephone, and confirmed by telegraph, mailgram or facsimile.,
no later than the first; normal working day following the event to the Director, Office of Inspection and Enforcement, Region II, or his designate with a written followup report within two weeks to the Director, Office of Inspec-tion and Enforcement, Region II (copy to the Director, Office of Management Information and Program Control).
(1) Failure of the Reactor Protective System to trip, as required, when a monitored parameter reaches the setpoint specified as the limiting safety system setting in the Technical Specifications.
(2) Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the Technical Specifications.
(3) Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary or primary containment.
(4) Reactivity anomalies involving disagreement with predicted value of reactivity balance under steady-state conditions greater than or equal to 1% ak/k; a calculated reactivity balance indicating shutdown margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds, or if subcritical, an unplanned reactivity.
insertion of more than 0.5% ak/k; or any unplanned criticality.
($) Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional require-
=ents of systems required to cope with accidents analyzed in the Safety Analysis Report.
(6) Personnel error or procedural inadequacy which prevents or could prevent, by.itself, the fulfillment of the fu.tctional requirements of systems required to cope with accidents analyzed in the Safety Analysis Report.
(7) Conditions arising from natural or man-made events that, as a direct result of the event, require unit shutdown, operation of safety systems, or other protective measures required by Technical Specifi-cations.
(8) Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the Safety Analysis Report or in the bases for the Technical Specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
9 y911190S M