ML20246K860

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Notice of Deviation from Insp on 890320-0419.Deviations Noted:Reg Guide 1.97 SER Did Not Ack Compliance W/Reactor Water Level Instrumentation Between Top of Core Support Plate & Top of Vessel of Main Steam Line Per Category 1
ML20246K860
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 05/05/1989
From: Miller H
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20246K858 List:
References
RTR-REGGD-01.097, RTR-REGGD-1.097 50-440-89-11, NUDOCS 8905180166
Download: ML20246K860 (1)


Text

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NOTICE OF DEVIATION Cleveland Electric Illuminating Docket No. 50-440 License No. NPF-58 The following deviation was identified during an inspection conducted on March 20 through April 19, 1989.

Regulatory Guide (RG) 1.97, Revision 2, Table 2, requires reactor water level instrumentation between the bottom of the core support plate and the lesser of the top of vessel or centerline of the main steam line to meet Category I requirements. Cleveland Electric Illuminating Company committed to complying with RG 1.97, Revision 2, in responses to the NRC on July 19 and April 15, 1983.

The NRC issued.a final RG 1.97 Safety Evaluation Report (SER) in December 1984 regarding the licensee's conformance to RG 1.97 and any acceptable deviations were noted in the SER.

Contrary to the above, the RG 1.97 reactor water level instrumentation at the Perry Plant meets Category 1 requirements only up to 40 inches below the centerline of the main steam line and Category III requirements for the remaining distance up to the main steam line centerline. The licensee stated that this issue had been accepted; however, the Perry RG 1.97 SER did not acknowledge this deviation (50-483/89011-01(DRS)).

This is a Deviation (Supplement I).

Please provide in writing within 30 days of the date of this Notice: (1) the  !

reason for the deviation; (2) the corrective actions that have been taken and  !

the results achieved; (3) the corrective actions that will be taken to avoid further deviations; and (4) the date when your corrective actions will be completed. Consideration may be given to extending the response time for good ,

cause shown.

Dated M C Mr1 i W HuygrtJ. Miller, Director Division of Reator Safety lpR05180166 090505 g ADOCK 05000440 PNU

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