ML20059N683

Notice of Violation from Insp on 900805-0915.Violation Noted:Monthly Operability Surveillance Testing Performed on RHR Sys/Lpci Pumps Per Procedure Qos 1000-2,Rev 12 Which Does Not Contain Acceptance Limits

ML20059N683
Person / Time
Site:	Quad Cities
Issue date:	10/05/1990
From:	Shafer W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20059N681	List: IR 05000254/1990014 ML20059N680 ML20059N683
References
50-254-90-14, 50-265-90-14, NUDOCS 9010170139
Download: ML20059N683 (1)

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NOTICEOFVIOLATQN lCommonwealthEdisonCompany- Docket No.- 50-254 Quad Cities Nuclear Station Docket No.-50-265  :

As a result of the inspection conducted from August.5 through September 15, 1990,-and in accordance with 10 CFR Part 2, Appendix C - General Statement, .

of_ Policy and Procedure for NRC Enforcement Actions (1990), the following- '

violations were identified:  ;

1.- 10 CFR 50, Appendix B, Criterion XI in part states that a test program shall be established to assure that all. testing required to demonstrate that structures, systems, and components will perform satisfactorily in '

service is identified and performed in accordance with written test _

procedures which incorporate the requirements and acceptance limits -

contained in the= applicable design documents.

Contrary to the above, monthly operability surveillance testing _was ,

performed on the Residual Heat Removal System / Low Pressure Coolant Injection (LPCI) pumps in accordance with procedure QOS 1000-2, Revision 12, Residual Heat Removal. System (RHRS) Pump Operability, which did not contain any i acceptance limits to demonstrate that the LPCI pumps were able to perform their design function.

a This is a -Severity Level IV violation (Supplement I) (254/90-014-01(DRP)). +

2. 10 CFR 50, Appendix B, Criterion III in part states that: " Design j

. changes, including field changes, shall be subject to design control measures commensurate with those applied to the original design and be approved by the organization that performed the original design'unless  ;

the applicant' designates another responsible organization." ,

. Contrary to the above, on April 28, 1978, the licensee installed wiring behind the Unit I control room panels that connected-auxiliary contacts for Emergency Core Cooling Systems (ECCS) and Emergency Diesel Generators (EDGs) to a common test point on a terminal. strip behind the_901-5 panel.

The installation was performed without doing the required design change }

reviews.

Thi s' ' is a Severity Level IV violation (Supplement I) (254/90-014-02(DRP)).

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: (1) the corrective actions that have been-

' s taken and the results achieved; (2) the corrective actions that will be taken '

i 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.

OCT 5 lose g((~

Dated . 0.~ Shaf Chief Reactor Pr ects Branch 1 9010170.139 901005 M j PDR ADOCK 05000254-O PNU

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