ML20058M049

Notice of Violation from Insp on 931021-25.Violation Noted:Licensee Did Not Assure That Design Basis Was Correctly Translated Into Specifications,Drawings,Procedures & Instructions

ML20058M049
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/14/1993
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20058M046	List: IR 05000313/1993031 ML20058M049
References
50-313-93-31, 50-368-93-31, EA-93-278, NUDOCS 9312200125
Download: ML20058M049 (2)

Text

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NOTICE OF VIOLATION Entergy Operations, Inc. Docket Nos. 50-316; 50-368 Arkansas Nuclear One License Nos. DPR-51; NPF-6  :

Units 1 and 2 EA 93-278 i

During an NRC inspection conducted October 21-25,_1993, violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, I the violations are listed below: l 10 CFR Part 50, Appendix B, Criterion III, states, in part, that ,

measures shall be established to assure that applicable regulatory l requirements and the design basis are correctly translated into e specifications, drawings, procedures, and instructions.  :

Unit 1 Safety Analysis Report Section 9.5.2.2 and the Unit's design -!

basis Upper Level Document ULD-1-SYS-04, which specify the design basis I' for the reactor building sump, state in part that the sump is covered with a screen of 0.132 inch by 0.132 inch mesh. These documents also  !

state that all of the components in the decay heat removal system, which l are used when the system is in the recirculation mode, are capable of operating in the presence of any debris which may pass through this  !

screen without plugging.

Unit 2 Safety Analysis Report Section 6.2.2.2 and the Unit's design i basis Upper Level Document ULD-2-SYS-04, which specify the design basis i for the reactor building sump, state in part that a series of screens l and supports completely covers the sump to prevent floating debris and -

high density particles from entering, and that the inner screen has a maximum diagonal opening of 0.09 inch. ,

I Contrary to the above, as of October 1,1993, the licensee did not j assure that the design basis was correctly translated into specifications, drawings, procedures and instructions. Specifically:

1. On October 1, 1993, 22 openings (6 inches in diameter by 3 inches high) in the curb around the Unit I reactor building sump were identified which were not screened and which would have allowed the passage of debris larger than 0.132 inches by 0.132 inches into the reactor building sump.

2. On October 1,1993, several openings around conduit penetrations through the Unit I reactor building sump screens, two tears in the screening material, and floor drains that were not screened were i

identified which would have allowed the passage of debris larger than 0.132 inches by 0.132 inches into the reactor building sump.

3. On October 22, 1993, several penetrations were identified along the lower structural support of the Unit 2 reactor building sump which bypassed the screens and provided a pathway for debris 9312200125 931214 I gDR ADOCK 05000313 PDR 4

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i larger than 0.09 inch by 0.09 inch to be swept into the sump.

1 (01013)

These violations represent a Severity Level III problem (Supplement I).

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l Pursuant to the provisions of 10 CFR 2.201, Entergy Operations, Inc., is  ;

! hereby required to submit a written statement or explanation to the U.S. '

l Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.  ;

l 20555 with a copy to the Regional Administrator, Region IV, 611 Ryan Plaza  !

l Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC Resident . ,

l Inspector at Arkansas Nuclear One, within 30 days of the date of the letter i transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each  !'

violation: (1) the reason for the violation', or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the i results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be ach:eved. If an adequate reply is not received within the time specified in this Notice, an.

order or a Demand for Information 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. Where good cause is shown, consideration will l be given to extending the response time. '

Under the authority of Section 182 of the Act, 42 U.S.C. 2232,. this response i shall be submitted under oath or affirmation.

Dated at Arlington, Texas

• this 14th day of December 1993 l

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