ML20203P331

Notice of Violation from Insp on 860224-28

ML20203P331
Person / Time
Site:	Vogtle
Issue date:	04/24/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20203P330	List: ML20203P329 ML20203P331 ML20203P332 ML20203P335
References
50-424-86-11, 50-425-86-06, 50-425-86-6, NUDOCS 8605070002
Download: ML20203P331 (3)

Text

E ENCLOSURE 1 NOTICE OF VIOLATION Georgia Power Company Docket Nos. 50-424, 425 Vogtle License Nos. CPPR-108, 109 The following violations were identified during an inspection conducted on February 24-28, 1986. The Severity Levels were assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

1. 10 CFR 50, Appendix B, Criterion XVI, as implemented by FSAR Chapter 17, Section 17.1.16, requires the licensee to establish measures to assure that conditions adverse to quality are promptly identified and corrected.

Contrary to the above, in September 1985, the licensee's measures had not assured prompt correction of deficiencies in their practices for maintaining their Design Criteria (DC), documents which prescribe the primary bases for.

the Vogtle plant design, up-to-date and fully accurate. Extensive numbers of Design Criteria had been found out-of-date (200 of 246) during the licensee's INP0 Construction Project Self Initiated Evaluation completed 1983. Corrective action was to have been completed by May 1983. Further errors involving omissions and failures to properly up-date DCs were identified by the licensee in their Module 4 Readiness Review (Findings 4-66, 4-67, and 4-75) submitted to the NRC in May 1985. Corrective action was to have been completed by July 1985. In September 1985, DC continued to contain uncorrected deficiencies involving inadequate updating as indicated by the following examples:

a. DC-1018 (Pipe Break Criteria - Interdiscipline) had not been updated to implement commitments described in a licensee letter to the NRC, dated April 26, 1984. Commitments in that letter include provisions to assure that no pipe support is located closer than five pipe diameters to a postulated pipe break,

b. DC-2702 (Post-Accident Sampling System) had not been corrected to reflect the intended design. DC-2702 prescribed an incorrect location for the residual heat removal (RHR) and containment spray sump post-accident sampling system lines.

c. DC-1204 (Safety Injection System), Section 6.0.2, incorrectly specified that the RHR lines from the containment sumps should contain two containment isolation valves (an out-dated requirement), whereas only one is required.

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

f I B605070002 860424 PDR ADOCK 05000424 PDR G

Georgia Power Company 2 Docket Nos. 50-424, 425 Vogtle License Nos. CPPR-108, 109

2. 10 CFR 50, Appendix B, Criterion V, as implemented by FSAR Section 17.1.5, requires that activities affecting quality be accomplished in accordance with drawings. 10 CFR 50, Appendix B, Criterion XVI, as implemented by FSAR Section 17.1.16, requires the establishment of measures that assure prompt identification and correction of deficiencies.

Contrary to the above,

a. Drawing requirements were not complied with in that, on August 30, 1985, RHR Isolation Valve Encapsulation Vessel 1-1205-V4-001, welds 49 and 50, were identified to the licensee as being smaller than specified by drawing IX4AH04-23-13. Subsequently, similarly located welds on similar Unit I and 2 vessels (RHR and CS Isolation Valve Encapsulation Vessels) were determined to be undersize to the drawing requirements and were documented on licensee Deviation Reports (DRs) MD-8721, 8723, and 8725.

b. Measures did not assure prompt identification and correction of the welding deficiencies in that.

(1) The licensee failed to identify the undersize weld conditions on Vessel 1-1205-V4-001, even though six unsatisfactory welding-related conditions had been identified for the vessel and weld 49 (one of the undersize welds) had been visually reinspected in accordance with DR MD-2264 (dated July 20, 1982 and considered resolved on March 19,1985).

(2) Although the undersize condition for welds 49 and 50 on Vessel 1-1205-V4-001 had been reported to the licensee on August 30, 1985, the deficient condition was not identified for correction on DRs (DR MD-8723) until February 1986, over five months later.

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

3. 10 CFR'50, Appendix B, Criterion V, as implemented by FSAR Section 17.1.5, requires that activities affecting quality shall be performed in accordance with instructions, procedures or drawings that include appropriate acceptance criteria for determining that important activities have been satisfactorily accomplished. RHR Isolation Valve Encapsulation Vessel 1-1205-V4-001 contains temporary shipping supports which are not intended to be left in the vessel. Vendor drawing B-81-22 includes instructions for removal of the supports (an activity necessary to assure the vessel and associated components perform as intended).

Contrary to the above, on February 28, 1986, the licensee did not document instructions, procedures or drawings that would assure that removal of the temporary supports in vessel 1-1205-V4-001 would be performed.

This is a Severity Level IV violation (Supplement II). This is applicable to Unit 1 only.

Georgia Power Company 3 Docket Nos. 50-424, 425

. Vogtle License Nos. CPPR-108, 109 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: (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 will be taken to avoid further violations; and (5) the date when full compliance will be achieved.

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: APR 2 41986

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