ML20245H745

Notice of Violation from Insp on 890118-0323.Violation Noted:Nuclear Engineering Did Not Initiate Deviation Rept as Required When Design Calculation 4572 & Procedure 44.020.204 Found W/Incorrect Head Correction Factor

ML20245H745
Person / Time
Site:	Fermi
Issue date:	04/21/1989
From:	Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20245H740	List: ML20245H736 ML20245H745 ML20245H749
References
50-341-89-07, 50-341-89-7, NUDOCS 8905030501
Download: ML20245H745 (1)

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NOTICE OF VIOLATION Detroit Edison Company Docket No. 50-341 Fermi 2 License No. NPF-43  ;

k I As a result of the inspection conducted on January 18 to March 23, 1989, and in accordance with 10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for NRC Enforcement Actions (1988), the following violation was 1dentified:

10 CFR 50, Appendix B, Criterion XVI, states in part that measures be established to assure that conditions adverse to quality are promptly identified and corrected. The identification of significant conditions adverse to quality, the cause of the condition, and the corrective actions taken shall be documented and reported to appropriate levels of management.

Contrary to the above, upon identification that Design Calculation 4572 and  !

procedure 44.020.204 both included an incorrect head correction factor, j Nuclear Engineering did not initiate a Deviation Event Report as required by {

Fermi procedures. Instead Nuclear Engineering notified the I&C department '

of the subject deficiency via a speed memo dated June 17, 1988. As a result, I&C did not schedule a revision for procedure 44.020.204 for completion until January 1989.

Consequently, the High Pressure Coolant Injection steamflow differential i pressure transmitter, E41-N0578, was subsequently calibrated on November 22,  !

1988, using the deficient procedure. This resulted in E41-N057B operating '

with a trip setpoint which exceeded the Technical Specification Table 3.3.2-2 allowable limit from November 22, 1988 to January 18, 1989.

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

Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this  :

office within thirty days of the date of this Notice a written statement or  ;

explanation in reply, including for each violation: (1) the corrective {

actions that have been taken and the results achieved; (2) the corrective 1 actions that will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.

IAPR 21 1989 Dated Richard C. Knop, Chief h

Reactor Projects Branch 3 l

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8905030501 890421 PDR Q

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