ML20214L010

Notice of Violation from Insp on 860929-1003 & 14-17

ML20214L010
Person / Time
Site:	Hatch
Issue date:	11/20/1986
From:	Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20214K987	List: IR 05000321/1986032 ML20214K985 ML20214L010
References
50-366-86-32, NUDOCS 8612020543
Download: ML20214L010 (3)

Text

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.o D s ENCLOSURE 1 NOTICE OF VIOLATION Georgia Power Company Docket No. 50-366 Hatch Unit 2 License No. NPF-5 During the Nuclear Regulatory Commission (NRC) inspection conducted on September 29 - October 3 and October 14-17, 1986, a violation of NRC requirements was identified. The violation involved incorrect welds being liquid penetrant examined during inservice inspection activities. 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:

10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings," require that activities affecting quality shall be prescribed by documented instructions, orocedures, or drawings, of a type appropriate to the circumstances and that the activities be accomplished in accordance with these instructions, procedures, or drawings, also Hatch Unit 2 Technical Specification 6.8.1.a and paragraph 1.0 of Appendix A to Regulatory Guide 1.33, Revision 3 require that general procedures be implemented for control of Inservice Inspection.

Contrary to the above, an activity affecting quality was not accomplished in accordance with general procedures for control of Inservice . Inspection i (ISI). On September 30, 1986, in the Hatch Unit 2 Drywell, at the 156' level, two ISI Liquid Penetrant (PT) examiners were observed mistakenly conducting examinations on two Loop "B" Reactor Recirculation System welds

2831-1RCM-12BE-3 Item No. 89.11, Pipe to Safe-End, isometric drawing number

! A-15 and 2B31-1RCM-28BS-2, Item No. B9.11, Safe-End to Elbow, isometric I drawing number A-18, which do not require examination during this outage.

The examiners were unaware that they had incorrectly identified the above welds as Loop "B" Reactor Recirculation System welds 2B31-1RC-12BR-E-5, Item No. 85.10, Reactor Vessel Nozzle to Safe-End, isometric drawing number A-15 and 2831-1RC-288-1, Item No. B5.10, Reactor Vessel Nozzie to Safe-End, isometric drawing number A-18 which do require examination during this outage. As a result, the welds which require examination would not have been examined but would have been reported as having been examined.

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

8612O20543 861120 POR ADOCK 05000321 G PDR

Georgia Power Company Docket No. 50-366 Hatch Unit 2 2 License No. NPF-5 Pursuant to the provisions of 10 CFR 2.201, Georgia 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 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 te extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed by Roger D. Walker Roger D. Walker, Director Division of Reactor Projects Dated a Atlanta, Georgia this day v? Mov. 1986

Georgia Power Company Docket No. 50-366 Hatch Unit 2 2 License No. NPF-5 Pursuant to the provisions of 10 CFR 2.201, Georgia 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 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 Roger Walker, Director M)

Division of Reactor Projects Dated at Atlanta, Georgia this 2flthday of Nov. 1986 i

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