ML19319B815
| ML19319B815 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 09/22/1977 |
| From: | George T, Lingenfelter J TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19319B726 | List: |
| References | |
| NUDOCS 8001270279 | |
| Download: ML19319B815 (2) | |
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(VENT Ot1CaiPtsoM g l Intermediate Range, Nuclear Instrument NI-3 was inoperable for connection j j to the Reacrimeter. This placed the unit in Action Statement 4a of
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Jacque Lingenfelter/ Tom George (4197'259-5000, Ext. 251 Naut P~oNc DVR #125-1 8o 012ro 277
TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STAIION l
SUPPLEMENTAL INFORMATION FOR LER NP-33-77-59 DATE OF EVE'iT: August 26, 1977 FACILITY: Davis-Besse Unit 1 IDENTIFICATI0K OF OCCURRENCE: NI-3 inoperable for connection to the React 1 meter.
Conditions Prior to Occurrence: The plant was in Mode 2, with Power (MWT) = 103, and Lead (MWE) = 0.
i Descriotion of 'ecurrence: At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> on August 26, 1977, Intermediate Range Nuclear Instrum';nt NI-3 which measures neutron flux in the core, was disconnected from the Reactoc Protection System.
It was connected to the Reacti=eter in order to make reactivity measurements. This placed the unit in Action Statement 4a of Technical Specification 3.3.1.1.
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Designation of Aeoarent Cause of Occurrence: NI-3 was disconnected for use with
- the Reactimete) in order to perform some minor physics testing to determine rod d
Analysis of Occtirrence: There was no threat to the health and safety of the public or to station personnel. NI-3 was monitored while connected to the Reactimeter, and Intermediate Range Nuclear Instrument NI-4 was operable during the period that NI-3 was disconnected.
Corrective Action: The power level was maintained at less than 5% Rated Thermal Power and at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on August 26, 1977, NI-3 was disconnected from the Reacti-i meter and recoc.nected to the Reactor Protection System. This removed the station from the Action Statement of Technical Specification 3.3.1.1.
i Failure Data: NI 3 was inoperah amone priweventdue to improper setpoint on the power supply NP-33-77-68.
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