ML20005F218

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Notice of Violation from Insp on 891105-1216.Violations Noted:Excess Flow Check Valve Surveillance Procedure Qis 47-1 Did Not Specify Valving Sequence for Returning Level Transmitter to Svc & on 891117,loss of Power Occurred
ML20005F218
Person / Time
Site: Quad Cities Constellation icon.png
Issue date: 01/08/1990
From: Shafer W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20005F216 List:
References
50-254-89-26, NUDOCS 9001160063
Download: ML20005F218 (1)


Text

NOTICE OF VIOLATION l

f comonwealth Edison Company Docket No. 50-254 l

As a result of the inspection conducted on November 5 through December 16, i

1989, and in accordance witn 10 CFR Part 2, Appendix C - General Statement t

I of Policy and Procedure for NRC Enforcement Actions (1989), the following violations were identified.

10 CFR Part 50 Appendix B, Criterion V, states that activities affecting

[

quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances, a.

Contrary to the above, an activity offecting quality was not adequately prescribed by documented procedure tn-that the Excess Flow Check Valve Surveillance procedure, QIS 47-1, did not specify the valving sequence for returning a level transmitter to service.

Consequently, on November 5, 1989, an ESF actuation.was generated while returning the i

1-263-58B reactor vessel level transmitter to service (254/89026-01a).

b.

Contrary to the above, an activity affecting quality was not adequately prescribed by documented procedure in that the out of service procedure-I for preparing the 1A 24/48 volt battery for its discharge test at the conclusion of the IB 24/48 volt battery discharge test did not properly sequence the realignment of the batteries.

Conseguently, on November 17, 1989, the A and B neutron monitoring instrumentation panels were simultaneoulsy deenergized, resulting in the-loss of power to both divisions of the intermediate range monitors and a reactor scram.

(254/89026-Olb).

Together these are considered a Severity Level IV violation (Supplement.1).

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

office within thirty days of the date of this Notice a written statement or explanation in reply, including-for each violation:- (1) corrective action taken and the results achieved; (2) corrective action to 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.

N 9 1990 YO

& 0/1,

Ddted

h. D. Shafef~, CNTef Reactor Pro'jects Branch 1 9001160063 900108 ADoCK0500g4 PDR o

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