ML20062J885
| ML20062J885 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/20/1982 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20062J676 | List: |
| References | |
| 50-327-82-05, 50-327-82-5, 50-328-82-05, 50-328-82-5, NUDOCS 8208160492 | |
| Download: ML20062J885 (2) | |
Text
APPENDIX A NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-327 & 50-328 Sequoyah I and 2 License Nos. DPR-77 & DPR-79 As.a result of the inspection conducted on March 29 - April 2,1982, and in accordance with the NRC Enforcement Policy, 47 FR 9987 (March 9, 1982), the following violations were identified.
A.
Technical Specification 6.4.1 requires a training and replacement training program to be maintained that meets or exceeds the requirements of ANSI N18.1-1971.
ANSI N18.1, paragraph 5.4, identifies the training and retraining required for all persons regularly employed in the nuclear power plant.
Administrative Procedure ( AI)-14, Plant Training Program, identifies the required training for each member of the operating staff.
Contrary to the above, required training for all persons regularly employed in th'e nuclear power plant has not been given in that, based on a records-review of 25 permanent plant staff members and 65 outage personnel, 40% of the plant staff and 35% of the outage personnel had not received all the required training.
This is a Severity Level IV Violation (Supplement I). A similar violation was brought to your attention in our letter dated February 13, 1981.
B.
10 CFR 50, Appendix B, Criterion V and the accepted QA Program (TVA-TR75-1, Revision 4), Section 17.2.5 requires that activities affecting quality shall be prescribed by documented procedures and shall be accomplished in accord-ance with these procedures.
The Operational QA Manual (0QAM) Part III, Section 6.1, paragraph 1.5, identifies the required general employee training and requires retraining necessary to ensure that personnel remain proficient.
AI-14, Plant Training Program, Revision 11, and DPM N79A7, Nuclear Plant General Training Program, revised November 24, 1981, imple-ments these requirements and identifies specific areas of training which require retraining to be initiated when changes to controlling documents occur or when other indicators reflect the need. Such areas include indus-trial safety, fire protection and prevention, introduction to QA/QC and TVA QA organizations, system of plant instructions, document control and quality assurance records, temporary conditions, plant modifications, procurement, and material control.
Contrary to above, retraining has never been conducted even though signi-ficant changes have occurred in several of the areas listed above.
This is a Severity Level IV Violation (Supplement I).
C208160492
$DRADOCKOh PDR
Tennessee Valley Authority 2
Docket Nos. 50-327 & 50-328 Sequoyah 1 and 2 License Nos. DPR-77 & DPR-79 C.
10 CFR 50, Appendix'B, Criterion II and the Accepted QA Program (TVA-TR75-1, j
Revision 4), Section 17.2.2 requires a training program to provide for
-indoctrination of personnel performing activities affecting quality as necessary to assure that. suitable proficiency is achieved and maintained.
The 0QAM Part III, Section 6.1, paragraph 6.1 states that -all persons regularly - employed in the nuclear power plant shall be trained in the i
area of Plant Quality Assurance Program.
i Contrary to the above, the training requirements for an outage craftsman specified in AI-14, Plant Training Program, Revision 11, does not require training in the Quality Assurance Program.
This is a Severity Level V Violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or denial-of the alleged viola-tions; (2) the reasons for the violations.if admitted; (3)'the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violatiens; and (5) the date when full compliance will be achieved. Consideration may be given to extending your response time for good ca'use shown.
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