ML20211A258

Notice of Violation from Insp on 861115-21

ML20211A258
Person / Time
Site:	Hatch
Issue date:	02/06/1987
From:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20211A236	List: ML20211A232 ML20211A258 ML20211A292
References
50-366-86-39, NUDOCS 8702190127
Download: ML20211A258 (2)

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ENCLOSURE 1 NOTICE OF VIOLATION i-Georgia Power Company Docket No. 50-366 Hatch- License No. NPF-5 j During the Nuclear Regulatory Consnission (NRC) inspection conducted on November 15-21~, 1986, a violation of NRC requirements was identified. The violation involved failure to determine the "as is" containment integrated leak rate of the Unit 2 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 listed below:

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

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

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that the "as is" (also called "as found") containment integrated leak rate i can be determined.

Where repairs or adjustments to the containment boundary prior to the Type A

! test- are necessary, Paragraph III.A.1(a) in conjunction with Paragraph c III.A.1(b) of Appendix J to 10 CFR 50 permit the repairs or adjustments 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

. 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 1

are included in the report to the Commission.

Contrary to the above, during the 1986 Unit 2 refueling outage, repairs r

or adjustments were made on two equipment hatchs and one isolation valve 4 limitorque actuator prior to the Type A test. The change in leakage rate resulting from the repairs or adjustments was not measured using local

, leakage test methods. Failure to quantify the change in leakage rate i resulting from these repairs or adjustments to the containment boundary

} renders the calculation of the "as is" containment integrated leakage rate j indeterminable.

v l This is a Severity Level IV Violation (Supplement I).

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} Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby j 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 l (for each violation): (1) admission or denial of the violation, (2) the reason i

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B702190127 070206 L i PDR ADOCK 05000321 G PDR i

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Georgia Power Company 2 Docket No. 50-366 Hatch License No. NPF-5 for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, 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 (A day of % ,,b i

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