ML20127L166

Notice of Violation from Insp on 850415-19

ML20127L166
Person / Time
Site:	Vogtle
Issue date:	05/28/1985
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127L154	List: ML20127L149 ML20127L166 ML20127L184
References
50-424-85-16, 50-425-85-16, NUDOCS 8506270772
Download: ML20127L166 (2)

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' ENCLOSURE 1 NOTICE OF VIOLATION Georgia Power Company Docket Nos. 50-424 and 425 License Nos. CPPR-108 and 109 Vogtle Unit 1 and 2 The following violations were identified during an inspection conducted on April 15-19, 1985. The Severity Levels were assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

1. 10 CFR 50.54(a)(1) requires the licensee to implement the quality assurance (QA) program described or referenced in its Safety Analysis Report (SAR).

Vogtle SAR Section 17.1.2 states that the Vogtle QA program is supported by written policies and procedures governing quality related functions and activities as referenced in the Vogtle Nuclear Plant Quality Assurance Manual (QA Manual). Table 17.1-1 V of the QA Manual outlines the policy and requirements for instructions, procedures, and drawings which describe activities affecting quality.

Contrary to the above, on April 17, 1985, cable support steel was found added to two electrical penetration enclosure boxes without drawings or instructions defining measures for the determination of when the manu-facturer's limit of 300 ft-lb moment was reached.

This is a Severity Level IV violation (Supplement II).

2. 10 CFR 50.54(a)(1) requires the licensee to implement the QA prograta described or referenced in its SAR. Vogtle SAR Section 17.1.2 states that the Vogtle QA program is supported by written policies and procedures governing quality related functions and activities as referenced in theXV Table 17.1-1 Vogtle Nuclear Plant Quality Assurance Manual (QA Manual).

of the QA Manual outlines the policy and requirements for a program to control material, parts or components that do not confom to specified requirements.

Contrary to the above on April 15, 1985, no guidelines or criteria were found in Procedure GD-T-01 to guide the Quality Control (QC) supervisors in determining the acceptability of deviation reports.

This is a Severity Level IV violation (Supplement II).

3. 10 CFR 50.54(a)(1) requires the licensee to implement the QA program described or referenced in its SAR. Vogtle SAR Section 17.1.2 states that the Vogtle QA program is supported by written policies and procedures governing quality related functions and activities as referenced Tablein17.1-1 the Vogtle Nuclear Plant Quality Assurance Manual (QA Manual).

XVI of the QA Manual which outlines the policy and requirements for a program to identify and correct conditions adverse to quality.

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Georgia Power Company 2 Docket Nos. 50-424 and 425 Vogtle Unit 1 and 2 License Nos. CPPR-108 and 109 Contrary to the above, on April 16, 1985, several deviation reports such as ED-08440, ED-06060, and ED-05471 were found to have dispositions that did not correct the condition reported.

This is a Severity Level IV violation (Supplement II).

4. 10 CFR 50.54(a)(1) requires the licensee to implement the QA program described or referenced in its SAR. Vogtle SAR Section 17.1.2 states that the Vogtle QA program is supported by written policies and procedures governing quality related functions and activities as referenced in the Vogtle Nuclear Plant Quality Assurance Manual (QA Manual). Table 17.1-1 V of the QA Manual outlines the policy and requirements for instructions, procedures and drawings which describe activities affecting quality.

Contrary to the above, on April 15, 1985, the racks for batteries 1AD1B, ICD 1B and IBD1B were found assembled, inspected and released to testing without meeting the manufacturer's requirements.

This is a Severity Level IV violation (Supplement II).

5. 10 CFR 50.7(e) requires the licensee to post foms NRC-3, " Notice to Employee" in a sufficient number of places to permit employees protected by this section to observe a copy on the way to or from their place of work.

10 CFR 21.6(a) requires the licensee subject to the regulation of this part to post the following documents in a conspicuous position on any premises within the United States where activities subject to this part are conducted: (1) the regulation in this part, (2) section 206 of the Energy Reorganization Act of 1974 and (3) procedures adopted pursuant to the regulations in this part.

Contrary to the above on April 19, 1985, the licensee had not posted Forms NRC-3 and Part 21 as prescribed in or near the Nuclear Power administration building, the service building and the maintenance building.

This is a Severity Level V violation (Supplement II).

Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply, including: () 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 will be taken to avoid furtherviolations;and(5)thedatewhenfullcompliancewil}beachieved.

Security or safeguards information should be submitted as an enclosure to facilitate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.

Date:

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