05000416/LER-2016-009

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LER-2016-009, Entry into Mode of Applicability with the Oscillation Power Range Monitor Upscale Settings Incorrectly Set
Grand Gulf Nuclear Station Unit 1
Event date: 03-27-2016
Report date: 01-05-2017
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
4162016009R00 - NRC Website
LER 16-009-01 for Grand Gulf, Unit 1, Regarding Entry into Mode of Applicability with the OPRM Upscale Settings Incorrectly Set
ML17228A275
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/16/2017
From: Neve D A
Entergy Operations
To:
Document Control Desk, Office of New Reactors
References
GNRO-2017/00030 LER 16-009-01
Download: ML17228A275 (5)


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Grand Gulf Nuclear Station Unit 1 05000416 On March 27, 2016, the Entergy, while returning the GGNS Unit 1 to power operations at the conclusion of Refueling Outage 21, reactor thermal power was allowed to exceed 16.8 percent without first fully calibrating the Oscillation Power Range Monitor (OPRM) to include the new limits required by the adoption and implementation of the Maximum Extended Load Limit Line Plus (MELLLA+) operating range. Specifically, the OPRM Upscale setting requirements specified in Technical Specification 3.3.1.1, Reactor Protection System (RPS) Instrumentation, Table 3.3.1.1-1, Reactor Protection System Instrumentation, Function 2, Average Power Range Monitors, Sub-Function f. OPRM Upscale were not fully met.

This error was subsequently discovered on November 17, 2016 during a review of General Electric Hitachi (GEH) Report 0000-0158-7807, Revision 0000, PRNM System DSS-CD Settings against the settings in GGNS Procedures 06-IC-1C51-R-0077A/B/C/D, Average Power Range Monitor Calibration.

REPORTABILITY

This event is reportable as a licensee event report (LER) in accordance with 10CFR50.73(a)(2)(i)(B) as an operation or condition prohibited by Technical Specifications and 10CFR50.73(a)(2)(v)(A) for the loss of safety function.

CAUSE

The causal evaluation for this event is ongoing and this LER will be supplemented upon completion of the causal analysis.

The direct cause of this event was the failure to ensure the required procedure changes were incorporated and performed prior to the unit entering the mode of applicability.

CORRECTIVE ACTIONS

Corrective actions included the addition of the condition to Limiting Condition for Operation tracking system to ensure resolution prior to a mode of applicability.

The condition has been added to Limiting Condition for Operation for tracking ensure resolution prior to restart.

SAFETY SIGNIFICANCE

There were no actual nuclear safety consequences or radiological consequences as a result of this calibration error.

No Technical Specification Safety Limits were violated.

PREVIOUSLY SIMILAR EVENTS

of Safety Function The causes and corrective actions implemented as a result of LER 2013-006-00 were reviewed and it has been determined that the corrective actions were acceptable and could not have prevented the event documented in this LER.