ML20210A563

Notice of Violation from Insp on 861107-14 & 1201-05

ML20210A563
Person / Time
Site:	Farley
Issue date:	01/26/1987
From:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20210A526	List: IR 05000348/1986025 ML20210A523 ML20210A563 ML20210A589
References
50-348-86-25, TAC-65399, NUDOCS 8702060496
Download: ML20210A563 (2)

Text

I ENCLOSURE 1 i NOTICE OF VIOLATION l Alabama Power Company Docket No. 50-348 Farley License No. NPF-2 During the Nuclear Regulatory Commission (NRC) inspection conducted on November 7

- 14, 1986, on site and December 1 - 5, 1986, in the Region II Office, a viola-tion of NRC requirements was identified. The violation involved the failure

! to determine the "as is" containment integrated leak rate of the Unit 1 primary

, containment. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions " 10 CFR Part 2, Appendix C (1986), the violation is l listed below:

i Paragraph III.A.1(a) of Appendix J to 10 CFR 50 and Paragraph 4.2 of ,

j ANSI-N45.4-1972, incorporated into the regulations by Paragraph III.A.3(a) i of Appendix J to 10 CFR 50, require that the Type A test shall be performed

! prior to making any repairs or adjustments to the containment boundary so that the "as is" (also called "as found") containment integrated leak rate can be determined.

Where repairs or adjustments to the containment boundary prior to the Type A test are necessary, ParagraphIII.A.1(a) in conjunction with Para-l graph III.A.1(b) of Appendix J to 10 CFR 50 permit the repairs or adjust-ments provided: (1) the change in leakage rate resulting from such repairs or adjustments is determined using local leakage testing methods; and (2)

, the corrective action taken, the change in leakage rate determined from the l local tests, and the "as is" containment integrated leakage rate determined from the local leakage and Type A test results are obtained, and the results

! are included in the report to the Connission.

Contrary to the above, during the 1986 Unit I refueling outage, repairs or adjustments were made to the fuel transfer tube blind flange and containment building equipment hatch prior to the Type A test. The change in leakage rate resulting from these repairs or adjustments was not measured using local leakage test inethods. Failure to quantify the change in leakage rate resulting from these repairs or adjustments to the containment boundary renders the calculation of the "as is" containment integrated leakage rate indeterminable.

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

Pursuant to the provisions of 10 CFR 2.201, Alabama Power Company is hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including (1) admission or denial of the violation, (2) the reason for the violation if 8702040496 870126 PDR ADOCK 05000340 0 PDR

Alabama Power Company 2 Docket No. 50-348 Farley License No. NPF-2 admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further viola-tions, and (5) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed by Luis A. Reyes Luis A. Reyes, Acting Director Division of Reactor Projects Dated at Atlanta, Georgia 1987 this y day of

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