ML20236J697

Notice of Violation from Insp on 980412-0530.Violation Noted:Several Conditions Adverse to Quality Associated W/Cr Ventilation Sys Were Not Promptly Corrected.Conditions Inappropriately Closed Out Before Adequate C/As Completed

ML20236J697
Person / Time
Site:	Farley
Issue date:	07/01/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20236J684	List: ML20236J683 ML20236J697 ML20236J702
References
50-348-98-03, 50-348-98-3, 50-364-98-03, 50-364-98-3, NUDOCS 9807080314
Download: ML20236J697 (2)

Text

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4 NOTICE OF VIOLATION 1

Southern Nuclear Operating Company. Inc. Docket Nos.: 50-348 and 50-364 Farley Nuclear Plant. Units 1 and 2 License Nos. NPF-2 and NPF-8 During an U.S. Nuclear Regulatory Commission (NRC) inspection conducted during \

the period April 12 through May 30. 1998, three violations of NRC requirements were identified. In accordance with the " General Statement of Policy arid Procedures for NRC Enforcement Actions." NUREG-1600, the violations are listed below:

A. 10 CFR Part 50. Appendix B Criterion XVI: Updated Final Safety Analysis Report, Section 17.2: and the J. M. Farley Plant Operations Quality s Assurance Policy Manual Chapter 16, require that the licensee take measures to assure that conditions adverse to quality are promptly identified and corrected. Such .-easures are to be taken to assure that the cause of the condition is determined and corrective actions are taken to preclude repetition.

Contrary to the above, several conditions adverse to quality associated with the Control Room Ventilation System (CRVS) were not promptly corrected. They were inappropriately closed out in mid-1995 to early 1996 before adequate corrective actions were completed. The licensee re-opened these issues in late 1997 to implement additional corrective actions needed to resolve them. The conditions adverse to quality not adequately corrected were:

(1) The control room exhaust isolation dampers were left open instead of closed. contrary to the original design basis (0 pen Item CRV-007).

(2) Areas adjacent to the MCR could be pressurized to greater than the MCR pressure and thereby allow unfiltered air inleakage into the MCR greater than assumed by the design calculation (0 pen Item CRV-010).

(3) MCR pressure testing did not adequately verify the MCR boundary integrity and therefore the administrative limit used to define allowable breaches was insufficient to ensure Technical Specification compliance (0 pen Item CRV-019).

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

B. Technical Specification 6.8.1.f requires written procedures be established. implemented, and maintained for the Security Program.

FNP-0-AP-42, " Access Control." Revision 26. requires that individuals be removed from the appropriate access list immediately upon termiro ion of need.

Enclosure 1 9807000314 900701 1 PDR ADOCK 05000348 N O PDR d

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l Notice of Violation 2 Procedure FNP-0-SP-11. ~ Badging Procedures." Revision 13. states that changes-in personnel access requirements caused by termination of employees will be reported immediately to the Security Site Manager.

The necessary action wiil be taken to remove the individual from access.

l Contrary to the above, during Spring 1998, procedures were not  ;

implemented in that the licensee failed to remove eight individuals from  ;

the appropriate access list immediately u)on termination of need. None of the eight individuals entered either tie protected or any vital areas ,

after termination.  !

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

C. 10 CFR 50.73(b)(3) states that a Licensee Event Report (LER) shall contain an assessment of the safety consequences and implications of the event. This assessment must include the availability of other systems or components that could have performed the same function as the components and systems that failed during the event.

10 CFR 50.73(d) states-that Licensee Event Reports must be prepared and ,

submitted within 30 days. l Contrary to the above. LER 50-348, 364/97-10. submitted on June 20. l 1997, did not adequately assess the safety consequences and implications '

of the possible failure of five mis-wired Motor-0]erated Valves at the -

Hot Shutdown Panel and did not include the availa)ility of other systems or components that could have performed tne same safe shutdown function.

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

Pursuant to the provisions of 10 CFR 2.201. Southern Nuclear Operating l Company. Inc. is hereby required to submit a written statement or explanation  ;

to the U.S. Nuclear Regulatory Commission. ATTN: Document Control Desk.

Washington. DC 20555. with a copy to the Regional Administrator. Region II.

and a copy to the NRC Resident Inspector. Farley Nuclear Plant, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).

This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for Violations A and B: (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 results achieved. (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will-be achieved. Your response may reference or include previously docketed correspondence. if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued j as to why the license should not be modified, suspended, or revoked, or why i such other action as may be proper should not be taken. . Where good cause is  !

shown, consideration will be given to extending the response time.

Enclosure 1 l

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