ML20057G129
| ML20057G129 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/08/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20057G127 | List: |
| References | |
| 50-298-93-08, 50-298-93-8, NUDOCS 9310200219 | |
| Download: ML20057G129 (3) | |
Text
.
APPENDIX A NOTICE OF VIOLATION Nebraska Public Power District Docket:
50-298 Cooper Nuclear Station License:
DPR-46 During an NRC inspection conducted on September 13-17, 1993, four 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:
A.
10 CFR Part 50, Appendix B, Criterion III, states in part that " design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews.,. Design control measures shall be applied to items such as the... delineation of acceptance criteria for inspections and tests."
Contrary to the above, the licensee failed to provide a documented design verification of several safety-related activities associated with the delineation and evaluation of acceptance criteria for motor-operated valve testing.
This is a Severity Level IV violation (Supplement I).
B.
10 CFR Part 50, Appendix B, Criterion V, states in part that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures or drawings."
Contrary to the above, the licensee failed to prescribe by procedure two safety-related activities essential for the proper evaluation of motor-operated valve testing.
These activities were adjustment of measurement uncertainties when measured thrust is outside of the calibration range and the comparison of extrapolated opening thrust to motor-operated valve limits for test acceptance. As a result of this deficiency, these activities were not performed.
This is a Severity Level IV violation (Supplement I).
l C.
10 CFR Part 50, Appendix B, Criterion XI, states, in part, that "a test program shall be established to assure that all testing required to demonstrate that structures, systems, and ccmponents 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 documents," and that
" test results shall be documented and evaluated to assure that test requirements have been satisfied."
9310200219 931006 PDR ADDCK 05000298 G
PDR i
i Contrary to the above, 29 motor-operated valves were returned to service following dynamic diagnostic testing based on improper acceptance criteria. -Each of the differential pressure tests were evaluated to a static test acceptance checklist that had been inadvertently inserted into the dynamic test procedure.
This is a Severity Level IV violation (Supplement I).
D.
10 CFR Part 50, Appendix B, Criterion XVI, states, in part, that
" 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."
Nebraska Public Power District "CNS M0V Program Plan," Revision 6, Section 5.0, " Test Program," states, in part, that "if any MOVs are found to be malfunctioning or not capable of functioning at design basis conditions during performance of the CNS MOV Test Program, the condition will be evaluated and processed in accordance with the following applicable CNS policies and procedures:
CNS Procedure 0.5.1, Nonconformance and Corrective Action CNS Procedure 0.5.2, Deficiency Reporting CNS Procedure 0.27, Operability of Systems, Structures,'and Components CNS Procedure 0.27.1, Operability Evaluations" Contrary to the above, during a Spring 1993 outage,. valve CS-M0V-05A, determined to be potentially malfunctioning by the presence of a significant thrust trace anomaly, was not evaluated as a nonconformance, not screened for operability, and not considered for any corrective actions.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Nebraska Public Power District is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.
20555, with a copy to the Regional Administrator, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, 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 Violation" 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 the time specified in this Notice, an order or a Demand for Information may be s
-. -.--,-,,,--,..i
. issued to show cause why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
Dated at Arlington, Texas this yt,* day of g 1993
,