ML20154Q503

From kanterella
Revision as of 09:51, 22 October 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Notice of Violation from Insp on 880326-0422.Violation Noted:Torus to Drywell Vacuum Breaker Test Solenoid Valves Incapable of Holding Pressure During Required Local Leak Rate Testing Due to Design Deficiencies
ML20154Q503
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 05/16/1988
From: Brownlee V
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20154Q498 List:
References
50-321-88-11, 50-366-88-11, NUDOCS 8806070042
Download: ML20154Q503 (2)


Text

. .. - _ - _ _ _ _ _ _ .

l l

l l .

ENCLOSURE 1 NOTICE OF VIOLATION Georgia Power Company Docket Nos. 50-321 and 50-366 Hatch Units 1 and 2 License Nos. DPR-57 and NPF-5 During the Nuclear Regulatory Comrgission (NRC) inspection conducted on March 26 - April 22, 1988, a violation of NRC requirements was identified.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1987), the violation is listed below:

Criterion 57 of Appendix A of 10 CFR Part 50 requires that each line that penetrates primary reactor containment and is neither part of the reactor coolant pressure boundary nor connected directly to the containment atmosphere have at least one containment isolation valve which shall be either automatic, or locked closed, or capable of remote operation.

Contrary to the above, prior to February 1988, torus to drywell vacuum breaker test solenoid valves (T48-F342A-L) were incapable of holding pressure during required local leak rate testing due to design defici encie s . Therefore, these valves were incapable of performing a containment isolation function as required by Criterion 57 for a closed system.

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

t '

Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN: Document Control Oesk, Washington, D.C. 20555, with a copy to the NRC Resident Inspector, Hatch Nuclear Plant, within 30 days of the date of the itetten,. transmitting this Notice. This reply should be clearly marked as ' I a "Reply to a Notice of Violation" and should include: (1) admission or denial of the violation, (2) the reasons for the violation 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 7ompliance will be achieved. Where good cause is shown, consideration

/

8806070042 880516 l PDR ADOCK 05000321  !

0 DCD

Georgia Power Company 2 Docket Nos. 50-321 and 50-366 Hatch Units 1 and 2 License Nos. DPR-57 and NPF-5 will be given to extending the response time. If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects Cated at Atlanta, Georgia this /4, day of May 1988 e

s s

/ . ~. s ,, .*,

. _ _ , , . - , _ _ _ __ _ . _ . _ , _ . _ _ _ . _ - . _ _ _ _ , _ . . ..,