ML15224A394
| ML15224A394 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/28/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15224A390 | List: |
| References | |
| 50-269-81-06, 50-269-81-6, 50-270-81-06, 50-270-81-6, 50-287-81-06, 50-287-81-6, NUDOCS 8107240364 | |
| Download: ML15224A394 (3) | |
Text
APPENDIX A NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-269, 270 & 287 Oconee 1, 2 & 3 License Nos. DPR-38, 47, & 55 As a result of the inspection conducted on March 23-27, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980),
the following violations was identified.
A.
10 CFR 50, Appendix B, Criterion II requires that the status and adequacy of the QA program shall be regularly reviewed.
The accepted QA program endorses ANSI 18.7-1976 as stated in Table 17.0-1.
ANSI 18.7-1976, Section 5.2.15, Review, Approval and Control of Procedures, requires plant procedures shall be reviewed by an individual knowledgeable in the area affected by the procedure no less frequently than every two years.
Contrary to the above, plant procedures are not reviewed every two years in that Administrative Policy Manual (APM) procedure 2.1, Document Control, and
.Station Directive 3.2.1, Performance of Periodic Testing Sampling, have not been reviewed since May 21, 1976 and April 2, 1976, respectively.
These two procedures are representative of six APM procedures reviewed and six station directives, reviewed none of which had not been reviewed within the previous two years.
This is a Severity Level V Violation (Supplement I.E).
B.
10 CFR 50.59 requires that a summary of the safety evaluation of each change to the facility made pursuant to this section be submitted to the NRC at least annually.
Contrary to the above, facility change safety evaluation summaries were not at least annually submitted to the NRC, in that the 1979 list of Oconee facility changes, which was submitted to the NRC on October 27, 1980, did not contain a summary of the safety evaluations for the li-s-ted modifica tions.
This is a Severity Level V Violation (Supplement I.E).
C.
10 CFR 50, Appendix B, Criterion XVI and Section 17.2.16 of the Accepted Quality Assurance Program requires that measures shall be established to assure that conditions adverse to quality are promptly identified and corrected.
50 80710-D OC 0500269 PDR
Duke Power Company 2
Docket Nos. 50-269, 270 & 287 Oconee 1, 2 & 3 License Nos. DPR-38, 47, & 55 Contrary to the above, conditions adverse to quality were not promptly identified and corrected in that inadequate fire protection storage of quality records located in the site file room was identified in Quality Assurance Departmental Audit 0-78-4, Item 7, dated June 14, 1978 and Audit 0-79-2, Item 2A, dated March 13, 1979; and corrective action for this problem area had not been conducted as of March 27, 1981. This matter had been addressed as an unresolved item in NRC Inspection Report 50-269,270, 287/79-10.
This is a Severity Level V Violation (Supplement I.E).
D.
10 CFR 50, Appendix B, Criterion XVII requires sufficient records shall be maintained to furnish evidence of activities affecting quality.
The records shall include the results of reviews.
The accepted QA Program, Section 17.2.17 requires each nuclear station to maintain adequate identifiable and retrievable quality assurance records.
Contrary to the above, records of the results of reviews were not maintained in that QA personnel perform reviews of QA Program procedures to ensure these procedures reflect current methods of conducting work practices but no records of the results of these reviews were maintained.
This was deter mined by direct questioning of QA personnel.
This is a Severity Level VI Violation (Supplement I.F).
E.
10 CFR 50, Appendix B, Criterion V requires activities affecting quality shall be prescribed by documented instructions, procedures or drawings and shall be accomplished in accordance with these instructions, procedures or drawings. The accepted QA Program, Section 17.2.5 implements this require ment. In addition, Technical Specification 6.4.1 requires that the station be operated and maintained in accordance with approved procedures.
The Administrative Procedures Manual (APM),
Section 2.5, Qualifications and Training of Personnel, paragraph 2.5.5.1 requires that periodic evaluations be conducted to assure that effectual training techniques are utilized.
Contrary to the above, activities affecting quality were not accomplished in accordance with procedures in that periodic evaluations to assure effectual training techniques have not been accomplished.
This is a Severity Level VI Violation (Supplement I.F).
Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within twenty-five days of the date of this Notice, a written state ment or explanation in reply, including:
(1) admission or denial of the alleged violations; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which
Duke Power Company 3
Docket Nos. 50-269, 270 & 287 Oconee 1, 2 & 3 License Nos. DPR-38, 47, & 55 will be taken to avoid further violations; and (5) the date when full compliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
Date: APR 28 1981