ML20059N683
| 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: |
| 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)).
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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
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reviews.
' s a Severity Level IV violation (Supplement I) (254/90-014-02(DRP)).
Thi s' 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:
(1) the corrective actions that have been-taken and the results achieved; (2) the corrective actions that will be taken s
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.
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OCT 5 lose Dated 0.~ Shaf Chief
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Reactor Pr ects Branch 1 9010170.139 901005 M
j PDR ADOCK 05000254-O PNU
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