ML16161A994
| ML16161A994 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/26/1988 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16161A993 | List: |
| References | |
| 50-269-88-03, 50-269-88-3, 50-270-88-03, 50-270-88-3, 50-287-88-03, 50-287-88-3, NUDOCS 8809080168 | |
| Download: ML16161A994 (2) | |
Text
ENCLOSURE NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-269, 270, & 50-287 Oconee License Nos. DPR-38, 47, & 55 During the Nuclear Regulatory Commission (NRC) inspection conducted on February 22-26, 1988, 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 (1988),
the violations are listed below:
A.
(f) and (k) require in part, that (1) qualification files for electrical equipment important to safety specify the performance requirements under conditions existing during and following a DBA; (2) electrical equipment important to safety shall be qualified by testing of, or experience with identical or similar equipment, and the qualification shall include a supporting analysis to show that the equipment to be qualified is acceptable; and (3) electric equipment important to safety which was previously qualified in accordance with "Guidelines for Evaluating Environmental Reactors" dated November 1979 (DOR Guidelines) need not be requalified to 10 CFR 50.49. DOR Guidelines, Section 5.2.2.,
allows the use of type tests to qualify equipment important to safety if the equipment is identical in design and material construction to the test specimen.
10 CFR 50.49(J) requires that records must be maintained in an auditable form.
Contrary to the above, the Oconee file, at the time of inspection, did not adequately document the performance characteristics for the Victoreen High Range Radiation Monitor System in that Insulation Resistances (IR) and Leakage currents for system components (cable, connectors, and penetration assemblies) were not adequately addressed. The installed system configura tion was not in the same configuration as the qualified tested system and deviations were not adequately evaluated as part of the qualification file; however, during the Enforcement Conference held on July 1, 1988, the licensee presented sufficient information in the form of test reports to establTsh that the installed configuration was qualifiable.
This is a Severity Level IV violation (Supplement I).
B.
10 CFR 50.49(f) and (k) respectively require, in part, that (1) each item of electric equipment important to safety shall be qualified by testing of, or experience with identical or similar equipment, and the qualification shall include a supporting analysis to show that the equipment to be qualified is acceptable; and (2) electric equipment important to safety which was previously qualified in accordance with "Guidelines for Evaluating Environmental Reactors," dated November 1979 (DOR Guidelines) need not be requalified to 10 CFR 50.49.
DOR Guidelines, Section 5.2.2, allows the use of type tests to qualify -equipment important to safety if the equipment is identical in design and material construction to the test specimen.
809080168 860826 PDR ADOCK 05000269 0
PNU
Duke Power Company 2
Docket Nos. 50-269, 270, & 50-287 Oconee License Nos. DPR-38, 47, & 55 Contrary to the above, at the time of inspection, the Reactor Building level transmitter junction box was not completely filled with oil and, therefore, was not in the as tested configuration.
The EQ file had no supporting analysis to show the equipment to be qualified in this configuration.
This is a Severity Level V violation (Supplement I).
C.
10 CFR 50, Appendix B, Criterion V requires that activities affecting quality be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstance and that such activities be accomplished in accordance with these instructions, procedures, or drawings.
Contrary to the above, the licensee's maintenance procedures were deficient in that the requirements specified in the Equipment Qualification Reference Index (EQRI) were not addressed properly in maintenance procedures.
Examples are:
(1) Requirement to ensure proper oil level in Reactor Building Level Transmitter junction box (2) Requirement to check for T-drains and grease reliefs on Limitorque actuators (3) Requirement concerning the lubrication frequency for motors This is a Severity Level V violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Oconee, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include [for each violation]: (1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where good cause is shown, consideration will be given to extending the response time.
If an adequate reply is not received within the time specified in this Notice, an order 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 should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION J. Nelson Grace Regional Administrator Dated at Atlanta, Georgia this rehday of 1
1988