ML17201Q429

From kanterella
Jump to navigation Jump to search
Notice of Violation from Insp on 890107-0317 & 0411. Violation Noted:Operator Not Adhering to DOP 6900-6 by Failing to Inform Control Room Prior to de-energizing Each Circuit & de-energized Circuits Prohibited by Procedure
ML17201Q429
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 04/21/1989
From: Mckenna E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17201Q428 List:
References
50-237-89-05, 50-237-89-5, 50-249-89-05, 50-249-89-5, NUDOCS 8905010134
Download: ML17201Q429 (1)


Text

NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-237 Docket No. 50-249 As a result of the inspection conducted on January 7, 1989, through March 17 and April 11, 1989, and in accordance with the General Policy and Procedures for NRC Enforcement Actions, (10 CFR Part 2, Appendix C), the following violations were identified:

1.

Dresden Technical Specification 6.2.A requires that plant operating procedures be prepared, approved and adhered to.

DOP 6900-6, 125 Volt DC Ground Detection - Unit 2, Revision 5, requires that while checking for grounds, the control room is to be informed prior to de-energizing each circuit and lists specific circuits that are not to be de-energized.

2.

Contrary to the above, on March 4, 1989, an operator did not adhere to DOP 6900-6 by failing to inform the control room prior to de-energizing each circuit and de-energized circuits specifically prohibited by the procedure.

This failure to follow procedure resulted in a Unit 2 reactor scram.

This is a Severity Level V violation (Supplement 1).

Technical Specification 6.2.A states that detailed written procedures covering preventive and corrective maintenance operations which could have an affect on the safety of the facility and testing requirements shall be prepared, approved and adhered to.

Contrary to the above, two rod control charging water check valves were inoperable (internal ball checks were missing) because of inadequate maintenanc~ procedures and were not detected because of the lack of

.prepared, approved testing procedures.

These valves appeared to have been inoperable since August 1986.

This is a Severity Level.IV violation (Supplement I).

The inspection showed that action had been taken to correct the identified violations and to prevent recurrence.

Consequently, no reply to the violations are required and we have no further questions regarding these matters.

APR 2 t 1989 Date 8905010134 8904?1

~DR ADOCK 0~605?:_~7

  • ~~

PDC Eileen M. McKenna, Acting Chief Reactor Projects Branch 1