ML20058A318
| ML20058A318 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/12/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20058A316 | List: |
| References | |
| 50-254-93-24, 50-265-93-24, NUDOCS 9312010042 | |
| Download: ML20058A318 (2) | |
Text
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4 NOTICE OF VIOLATION Commonwealth Edison Company Docket Nos. 50-254; 50-265 Quad Cities Nuclear Plant Licenses No. DPR-29; No. DPR-30 Units 1 and 2 During an NRC inspection conducted July 28-30, August 2-4, and August 9-20, 1993, violations of NRC requirements were identified.
In accordance with'the
" General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C, the violations are listed below:
i 1.
10 CFR 50, Appendix B, Criterion XI states, in.part, 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 applicable design i
documents.
QAP 1500-17, " Post-Maintenance Testing / Verification Procedure",
a.
Revision 4, required that post-maintenance tests be specified, performed and documented following maintenance activities.
Contrary to the above, on April 26, 1993, the licensee failed to specify the required post-maintenance testing associated with nuclear work request #Q99959 (Bus 22 - 4 kV breakers) and-testing was not performed (254/265-93024-02A(DRS)).
b.
Technical Specification Table 3.2-2, an operation analysis division (OAD) relay setting order, and procedure QC0 ADS 100-1,
" Rock River Division 0AD Undervoltage Relay Calibration," Revision 0, required a setting of 87 volts 5% (82.65 to 91.35 volts) for the 4kV emergency bus undervoltage relays.
Contrary to the above, as of March 18, 1993, the licensee failed to implement _the above design requirements and acceptance limits
~during testing of the 4kV buses 23-1 and 24-1 undervoltage relays.
The calibration data sheets used.specified 83 volts i 5% (79 to 87 volts) (254/265-93024-028(DRS)).
2.
10 CFR 50, Appendix B, Criterion V states that activities affecting quality shall be prescribed by documented instructions or-procedures, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions or procedures.
Nuclear Operations Directive (N00) OP.16, "DC Ground Action Requirements," dated October 1,1989, provided action requirements for'~
plant operation with electrical grounds on safety-related dc systems.
Contrary to the above, from October 1,1989, to August 20, 1993, the licenste failed to address N00 ground requirements as _specified in the N0D and subsequent plant procedures (254/265-93024-03(DRS)).
9312010042 931112 PDR ADOCK 05000254 G
-Notice of Violation 2
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i 3.
10 CFR 50, Appendix B, Criterion XVI states, in part, measures. shall be established to assure that conditions adverse to quality, such as, failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.
~
a.
Procedure QCAP 2300-6, " Station Commitment and Action item Tracking," Revision 0, required that operating experience, such as, General Electric's service information letters (SILs) be evaluated within 90 days.
Contrary to the above, prior to August 20, 1993, the licensee failed to promptly evaluate / identify appropriate corrective actions for applicable SIls (254/265-93024-04A(DRS)).
b.
Contrary to the above, from November 30, 1991, to August 20, 1993, i
the licensee failed to complete corrective action inspections to identify / replace defective SBN switches on safety-related and important to safety 4kV breakers (254/265-93024-04B(DRS)).
j c.
Contrary to the above, from December 16, 1991, to August 20, 1993, a number of broken / damaged parts were identified that indicated improper handling of safety-related and important to safety 4kV breakers.
Improper handling of 4kV breakers had previously been j
recorded by licensee personnel, but no corrective action were i
taken to resolve this condition (254/265-93024-04C(DRS)).
These violations represent a Severity Level IV problem (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Commonwealth Edison Company is hereby required to submit a written statement or explanation to the U.S.
j Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C.
20555 with a copy to the Regional Administrator, Region Ill, and a. copy to the NRC Resident Inspector at the facility that is the subject'of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked as a " Reply to a Notice of violatinn and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the.
corrective steps that have been taken and the results achieved, (3) the-corrective steps that will be taken to avoid further violations,.and (4) the date when full compliance will be achieved.
If an adequate reply is not received within tne time specified in this Notice, an order or a Demand for Information may be issued to show cause why the license should not be modified, suspended, or revoked, or why such other action as may be proper
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should.not be taken. Where good cause is shown, consideration will be given to extending the response time.
Dated at Glen Ellyn, Illinois j
this 12th day of November,1993 4
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