ML18065A251
| ML18065A251 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/21/1990 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18065A249 | List: |
| References | |
| 50-255-90-05, 50-255-90-5, NUDOCS 9511090064 | |
| Download: ML18065A251 (1) | |
Text
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. NOTICE OF VIOLATION Consumers Power Company Palisades Nuclear Plant Docket No. 50-255 Litense No. *DPR-20 As a result of the inspection conducted during January 22 through March 2, 1990, and in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions", 10 CFR Part 2, Appendix C, (1989) (Enforcement Policy) the following violations were identified:
- a.
10 CFR 50, Appendix B, Criterion XVI, "Corrective Action" requires that measures be established to assure that conditions adverse to quality, including nonconformances, are promptly identified and corrected.
In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition. The corrective action taken shall be documented and reported to appropriate levels of management.
Contrary to the above, Consumers Power Company {CPCo) failed to assure that the corrective action taken in response to a previously identified EQ Severity Level IV violation was adequate in that the licensee failed to demonstrate the qualification of the Bendix potted connectors used on Vi king e lectri ca 1 penetrations.
Insulation resistance (IR) measurements
.were n6t taken during the accident portion of the EQ test. These measurements are necessary to ensure that instrument accuracy requirements are met. and tbat low voltage contra l circuits wi 11 perform their safety function during accident conditions.
This is a Severity Level IV violation (Supplement ID)
(50-255/90005-03(DRS)).
b..
10 CfR 50.49, Paragraph f, requires each item of el~ctrical equipment important.to safety be qualified by'testing or testing and analysis.
Contrary to the above, the licensee identified Auxiliary Feedwater (AFW) control circuit relays R/0727 and R/0749, located in a harsh environment, that were omitted from the EQ Master Equipment List and consequently not
- qualified by testing or testing and analysis.
This is a Severity Level IV violation (Supplement ID)
(50-2o5/9005-04(DRS)).
Pursuant to the provisions of 10 CFR 2.201, you a~e 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 steps that have been taken and the results achieved; (2) the corrective steps that will be taken to avoid further violations; ~nd (3) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
9511090064 900322 PDR ADOCK 05000255 G
PDR H. J. Mi lE:r, Director Division of Reactor Safety